FINAL SAFETY ANALYSIS REPORT CHAPTER 1 INTRODUCTION AND GENERAL DESCRIPTION OF THE PLANT
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FINAL SAFETY ANALYSIS REPORT CHAPTER 1 INTRODUCTION AND GENERAL DESCRIPTION OF THE PLANT
FINAL SAFETY ANALYSIS REPORT CHAPTER 1 INTRODUCTION AND GENERAL DESCRIPTION OF THE PLANT CCNPP Unit 3 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 1.0 Introduction And General Description of the Plant INTRODUCTION AND GENERAL DESCRIPTION OF THE PLANT This chapter of the U.S. EPR Final Safety Analysis Report (FSAR) is incorporated by reference with supplements as identified in the following sections. CCNPP Unit 3 1-1 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 1.1 Introduction INTRODUCTION This section of the U.S. EPR FSAR is incorporated by reference with the following supplements. This Final Safety Analysis Report is submitted to the Nuclear Regulatory Commission as part of an application for a Class 103 combined license (COL) to construct and operate a nuclear power facility under the provisions of 10 CFR 52, Subpart C. {This FSAR is also being submitted to the Nuclear Regulatory Commission to support the necessary Materials Licenses requested in the COL Application Letter (UNE, 2008) to receive, possess and use byproduct, source and special nuclear material under 10 CFR 30, 10 CFR 40 and 10 CFR 70, respectively.}This nuclear power facility is designated {Calvert Cliffs Nuclear Power Plant (CCNPP) Unit 3.}This FSAR incorporates the FSAR prepared for the design certification application for the AREVA evolutionary pressurized water reactor, (herein referred to as the U.S. EPR). AREVA NP, the entity sponsoring the design certification application for the U.S. EPR, submitted a revised U.S. EPR design certification application to the NRC on August 31, 2010 (AREVA, 2010). Upon approval and issuance of the design certification for the U.S. EPR, the approved version of the FSAR for the U.S. EPR and the associated Appendix to 10 CFR 52 documenting the design certification for the U.S. EPR are incorporated by reference into this COL application. Within each section, or subsection, only supplemental information or departures from the certified design are presented. If the U.S. EPR provides sufficient information, this FSAR will state ”This section of the U.S. EPR FSAR is incorporated by reference” at the section (i.e. X.Y) level and ”No departures or supplements” at the highest subsection level where such a statement can be made. Likewise, if a section contains additional information, a statement is provided at the section level to identify if departures or supplements are provided. Section and subsection numbering is only provided to the extent necessary to provide sufficient context to correlate the information provided in this FSAR with the information provided in the U.S. EPR FSAR. Supplemental information is provided in three forms. Additional information, such as this text, is provided in the appropriate section. The second form is COL Item responses. COL Items are statements in the U.S. EPR FSAR that indicate that the COL applicant must provide additional information. Each applicable COL Item is restated in the equivalent section/subsection in this FSAR and information to address the COL Item is provided. The final type of supplemental information provided in this FSAR is to address conceptual design information provided in the U.S. EPR FSAR. Conceptual design information is presented in the U.S. EPR FSAR enclosed in double brackets ”[[ ]]”. As stated in the U.S. EPR FSAR, the conceptual design information is outside the scope of the U.S. EPR standard design, and is not submitted for certification as part of that document. Like COL Items, the conceptual design information is restated in this FSAR followed by the site specific information. Departures from the U.S. EPR FSAR are identified in the applicable sections of the COL Application. {U.S. EPR nuclear power plants that are licensed, constructed, and operated in cooperation with UniStar Nuclear Operating Services LLC (UniStar Nuclear Operating Services) are standardized to the extent practical. This allows for a standardized FSAR. Information that is unique to {CCNPP Unit 3} is enclosed in braces ”{ }”. Information not enclosed in braces is generic for all UniStar Nuclear Operating Services facilities. Minor changes are made within the generic text that are not identified as site specific. These includes figure and table numbers, which are organized sequentially within sections, and minor grammatical changes necessary to support introduction of site specific text.} CCNPP Unit 3 1-2 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 Introduction The U.S. EPR FSAR includes the following COL Item in Section 1.1: A combined license (COL) applicant that references the U.S. EPR design certification and proposes a multiunit license application will provide the changes and additional information needed to license a multiunit plant. This COL Item is addressed as follows: {This COL application is for a single unit U.S. EPR. As such, no changes or additional information are needed to address this COL Item.} 1.1.1 Plant Location The U.S. EPR FSAR includes the following COL Item in Section 1.1.1: A COL applicant that references the U.S. EPR design certification will identify the specific plant site location. This COL Item is addressed as follows: {CCNPP Unit 3 is colocated with two currently licensed reactors (CCNPP Units 1 and 2). CCNPP Unit 3 is located south of the existing nuclear power plant on the existing CCNPP site. The CCNPP site consists of 2070 acres (838 hectares) in Calvert County, Maryland, on the west bank of Chesapeake Bay, approximately halfway between the mouth of the bay and its headwaters at the Susquehanna River. As reflected in Figure 2.1-1, CCNPP Unit 3 is within the CCNPP Units 1 and 2 Exclusion Area Boundary and the CCNPP Units 1 and 2 Independent Spent Fuel Storage Installation Exclusion Area Boundary. The site is approximately 40 mi (64 km) southeast of Washington D.C. and 7.5 mi (12 km) north of Solomons Island, Maryland. Figure 1.1-1 through Figure 1.1-3 illustrate the location of the site, and the arrangement of the three units. CCNPP Unit 3 shares the following structures, systems, and components with CCNPP Units 1 and 2: ᅁ Offsite transmission system ᅁ Chesapeake Bay intake channel and embayment ᅁ Meteorological tower ᅁ Emergency Operations Facility (EOF) ᅁ Barge dock In accordance with 10 CFR 52.79(a)(31) (CFR, 2008), the following provides an assessment of the potential hazards to the structures, systems, and components (SSCs) important to safety of operating units resulting from construction activities at a multiunit site and identifies that managerial and administrative controls are to be used to provide assurance that the limiting conditions for operation (LCOs) at the operating units, are not exceeded as a result of new plant construction activities. The managerial and administrative controls include coordination, with CCNPP Units 1 and 2, of construction activities which have the potential for causing CCNPP Units 1 and 2 to exceed LCOs or have an adverse impact on the availability of safety and risk significant SSCs. CCNPP CCNPP Unit 3 1-3 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 Introduction Units 1 and 2 procedures and processes are currently in place to control activities that could affect compliance with an LCO or availability of safety and risk significant SSCs, e.g., equipment clearance and tagout procedures, access controls, and switchyard controls. The potential hazards associated with CCNPP Unit 3 construction activities include, but are not limited to general construction activities such as site exploration, grading, clearing, and installation of drainage and erosioncontrol measures; boring, drilling, dredging, pile driving and excavating; transportation, storage and warehousing of equipment; construction, erection, and fabrication of new facilities; and connection, integration, and testing. Specific potential impacts to CCNPP Units 1 and 2 SSCs include the following: ᅁ Relocation and construction of transmission lines/towers ᅁ Construction of Sheetpile wall and Intake Pipes on the shore of the Chesapeake Bay next to the embayment for the intake structures for CCNPP Units 1 and 2 ᅁ Meteorological data transmission modifications (electrical and instrumentation tieins and connections to provide input to CCNPP Unit 3 facilities) ᅁ Modification to the existing Emergency Operations Facility to accommodate CCNPP Unit 3 Emergency Planning activities The majority of the CCNPP Units 1 and 2 SSCs important to safety are contained and protected within safetyrelated structures. Managerial controls will protect these internal SSCs from postulated construction hazards by maintaining the integrity and design basis of the safetyrelated structures and foundations. Heavy load drop controls, crane boom failure standoff requirements, ground vibration controls and construction generated missiles controls are examples of managerial controls that shall be established to provide this reasonable assurance. Other managerial controls shall be established to ensure that hazardous materials and gasses are controlled, cooling water supplies are protected, instrumentation is protected from vibrations, and the SSCs are protected from site excavation issues. These managerial controls prevent or mitigate external construction impacts that could affect these SSCs. These controls also prevent or mitigate unnecessary challenges to CCNPP Units 1 and 2 safety systems that could be caused by potential CCNPP Unit 3 construction activity hazards, such as disruption of offsite transmission lines or impact to cooling water supplies. Onsite construction activities with potential safety significance to the operating units shall also be addressed in accordance with established CCNPP Unit 1 and 2 procedures and processes, as described above. Construction impacts on security controls are addressed in the CCNPP Unit 3 Security Plan. The CCNPP Unit 3 Security Plan is provided in Part 8 of the COL application.} Additional site details are provided in Chapter 2. 1.1.2 Containment Type No departures or supplements. 1.1.3 Reactor Type No departures or supplements. CCNPP Unit 3 1-4 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 1.1.4 Introduction Power Output No departures or supplements. 1.1.5 Schedule The U.S. EPR FSAR includes the following COL Item in Section 1.1.5: A COL applicant that references the U.S. EPR design certification will provide the estimated schedules for completion of construction and commercial operation. This COL Item is addressed as follows: {The following major activities are scheduled*: Order Ultra Heavy Forgings for Reactor Vessel and NSSS Components Submit Environmental Report for CCNPP Unit 3 Submit Certificate of Public Convenience and Necessity (CPCN) Application to the State of Maryland Submit Design Certification Application for the U.S. EPR Submit Remainder of COL Application for CCNPP Unit 3 State of Maryland Issues CPCN for CCNPP Unit 3 NRC Issues Design Certification for U.S. EPR NRC Issues COL Plant Construction Starts Construction Complete Plant Startup Testing Begins Commercial Operation * dates are provided as representative projections 1.1.6 April 2006 (complete) July 2007 (complete) November 2007 (complete) December 2007 (complete) March 2008 (complete) December 2008 October 2010 March 2011 April 2011 July 2015 July 2015 December 2015} Format and Content 1.1.6.1 Regulatory Guide 1.206 This FSAR follows the U.S. EPR FSAR organization and numbering. The U.S. EPR FSAR was written in accordance with the format and content of Regulatory Guide 1.206, (NRC, 2007). This FSAR provides departures and supplemental information from the standard U.S. EPR design that is unique to the {CCNPP Unit 3} project. If the information provided in the U.S. EPR FSAR sufficiently addresses the Regulatory Guide 1.206 content for {CCNPP Unit 3}, this FSAR will state ”No departures or supplements” at the highest section level where such a statement can be made. In addition, this FSAR may add a final section or subsection (when necessary) for references made within this document. References will be provided if they are used in this FSAR even if they were identified within the U.S. EPR FSAR. 1.1.6.2 Standard Review Plan No departures or supplements. CCNPP Unit 3 1-5 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 1.1.6.3 Introduction Text, Tables and Figures Tables and figures are identified by the section or subsection in which they appear and are numbered sequentially. For example, Table 1.1-1 and Figure 1.1-1 would be the first table and figure appearing in Section 1.1. Figures consist of diagrams, plots, pictures, graphs or other illustrations. Tables and figures are located at the end of the applicable section (X.Y) immediately following the text. 1.1.6.4 Numbering of Pages Pages are numbered sequentially within each chapter. 1.1.6.5 Proprietary Information This document contains no proprietary information. 1.1.6.6 Acronyms Table 1.1-1 provides a list of acronyms that are used in this document. 1.1.6.7 COL Information Items The COL Items in the U.S. EPR FSAR are discussed in Section 1.8. 1.1.6.8 Tense This section is added as a supplement to the U.S. EPR FSAR. This FSAR is a licensing basis document that will control plant design and operations after the COL is issued and is generally written in the present tense. Plant design and configuration are described in the present tense although the plant is not yet built. Similarly, programs, procedures, and organizational matters are generally described in the present tense although such descriptions may not yet be implemented. Accordingly, the use of the present tense in this FSAR should be understood as describing the plant, programs and procedures, and organization as they will exist when in place, and not as a representation that they are already in place. 1.1.7 References {This section is added as a supplement to the U.S. EPR FSAR. AREVA, 2010. Submittal of Revision 2 of the U.S. EPR Final Safety Analysis Report for Design Certification, S. Sloan letter to U. S. Nuclear Regulatory Commission Document Desk, dated August 31, 2010. CFR, 2008. Title 10, Code of Federal Regulations, Part 52.79, Contents of Applications; Technical Information in Final Safety Analysis Report, U.S. Nuclear Regulatory Commission, 2008. NRC, 2007. Combined License Applications for Nuclear Power Plants (LWR Edition), Regulatory Guide 1.206, Revision 0, U.S. Nuclear Regulatory Commission, March 2007. UNE, 2008. UniStar Nuclear Energy Letter, G. Gibson to U.S. Nuclear Regulatory Commission, UN#08003, Submittal of Revision 2 to the Partial Combined License Application for the Calvert Cliffs Nuclear Power Plant, Unit 3, dated March 14, 2008.} CCNPP Unit 3 1-6 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 Introduction Table 1.1-1— {Acronyms Used in this Document} (Page 1 of 6) Acronym Description χ/Q Atmospheric Dispersion Value A/E Architect – Engineer AASHTO American Association of State Highway and Transportation Officials AB Access Building ACI American Concrete Institute AFDD Accumulated Freezing DegreeDays ALOHA Areal Locations of Hazardous Atmospheres ANS American Nuclear Society ANSI American National Standards Institute ANSS Advanced National Seismic Network AOV AirOperated Valve AQCR Air Quality Control Region ASCE American Society of Civil Engineers ASHRAE American Society of Heating, Refrigerating, and Air Conditioning Engineers AWWA American Water Works Association BE Best Estimate BF Butterfly Valve BGE Baltimore Gas and Electric BMA Brunswick Magnetic Anomaly BWI Baltimore/Washington International C/NM Consumable/NonMetallic CAM Continuous Air Monitor CBBT Chesapeake Bay Bridge Tunnel CBIS Common Basemat Intake Structures CCNPP Calvert Cliffs Nuclear Power Plant CD Certified Design CEUS Central and Eastern United States CLSZ CharlevoixLa Malbaie Seismic Zone CK Check Valve CPCN Certificate of Public Convenience and Necessity CPT Cone Penetrometer Test CR Control Room CRE Control Room Envelope CRR Cyclic Resistance Ratio CSDRS Certified Seismic Design Response Spectra CSR Cyclic Stress Ratio CTI Cooling Tower Institute CVSZ Central Virginia Seismic Zone D.C. District of Columbia CCNPP Unit 3 1-7 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 Introduction Table 1.1-1— {Acronyms Used in this Document} (Page 2 of 6) Acronym Description D/Q Deposition Factor DAC Derived Air Concentration DC Direct Current DCPLNG Dominion Cove Point Liquefied Natural Gas DI Diaphragm Valve DNAG Decade of North American Geology DOE Department of Energy DOT Department of Transportation EC Erosion/Corrosion ECFS East Coast Fault System ECL Effluent Concentration Limits ECMA East Coast Magnetic Anomaly EMC Electromagnetic Compatibility EPA Environmental Protection Agency EPIX Equipment Performance and Information Exchange EPR Evolutionary Power Reactor EQ Environmental Qualification ER Environmental Report or Electrical Resistivity ERC Estuarine Research Center ES Engineered Safeguards ESP Early Site Permit EST Earth Science Team ESWB Essential Service Water Building ETR Energy Transfer Ratio FERC Federal Energy Regulatory Commission FFD Fitness for Duty FHA Fire Hazards Analysis FIRS Foundation Input Response Spectra FOS Factor of Safety FPE Fire Protection Engineer GB Globe Valve GMRS Ground Motion Response Spectra GSA Geological Society of America GT Gate Valve HF High Frequency HMR Hydrometeorological Report HO Hydraulic Operated HPS Health Physics Society ICEA Insulated Cable Engineers Association CCNPP Unit 3 1-8 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 Introduction Table 1.1-1— {Acronyms Used in this Document} (Page 3 of 6) Acronym Description ICRP International Commission on Radiological Protection ID Identification IDLH Immediately Dangerous to Life and Health IRC Independent Review Committee ISFSI Independent Spent Fuel Storage Installation JFD Joint Frequency Distribution JPM Job Performance Measures KKS Kraftworks Kennzeichen System LB Lower Bound LERF Large Early Release Frequency LF Low Frequency LFL Lower Flammability Limit LiDAR Light Detection and Ranging LLC Limited Liability Company LNG Liquefied Natural Gas LPS Layer Parallel Shortening LSS Low Safety Significance LSZ Lancaster Seismic Zone MA Manual Actuated MD Maryland MDE Maryland Department of Environment MDNR Maryland Department of Natural Resources MED Master Equipment Database MMBO Million Barrels of Oil MEDEVAC Medical Evacuation MEOW Maximum Envelopes of Water MGS Maryland Geological Survey MHHW Mean Higher High Water MLLW Mean Lower LowWater MLW Mean Low Water MMI Modified Mercalli Intensity MOM Maximum of the MEOWS MPSSZ Middleton PlaceSummerville Seismic Zone MRFF Maintenance Rule Functional Failure MSL Mean Sea Level MSS Medium Safety Significance NAAQS National Ambient Air Quality Standards NAS Naval Air Station NEC National Electrical Code CCNPP Unit 3 1-9 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 Introduction Table 1.1-1— {Acronyms Used in this Document} (Page 4 of 6) Acronym Description NEI Nuclear Energy Institute NERC North American Electric Reliability Corporation NGVD 29 National Geodetic Vertical Datum of 1929 NHC National Hurricane Center NIC National Ice Center NIOSH National Institute for Occupational Safety and Health NJ New Jersey NLSWE Nonlinear Shallow Water Equations NOAA National Oceanic and Atmospheric Administration NP NonProprietary NPDES National Pollution Discharge Elimination System NPRDS Nuclear Plant Reliability Data System NRC Nuclear Regulatory Commission NRCS U.S. National Resources Conservation Service NWS National Weather Service NYAL New York – Alabama Lineament OBE Operating Basis Earthquake OCR Over Consolidation Ratio ODCM Offsite Dose Calculation Manual OJT OntheJob Training OSHA Occupational Safety and Health Administration P Proprietary PA Pilot Actuated PCP Process Control Program PEPCO Potomac Electric Power Company PGA Peak Ground Acceleration PJM Pennsylvania, New Jersey, and Maryland Regional Transmission Organization PL Plug Valve PMH Probable Maximum Hurricane PMSS Probable Maximum Storm Surge PMT Probable Maximum Tsunami PMWP Probable Maximum Winter Precipitation PPRP Power Plant Research Program PSAR Preliminary Safety Analysis Report PSHA Probabilistic Seismic Hazard Analysis PSP Physical Security Plan PST PreService Testing PTS Pressurized Thermal Shock QAPD Quality Assurance Program Description CCNPP Unit 3 1-10 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 Introduction Table 1.1-1— {Acronyms Used in this Document} (Page 5 of 6) Acronym Description QC Quality Control RCA Radiologically Controlled Area RCTS Resonant Column Torsional Shear RD Rupture Disk Valve REMP Radiological Environmental Monitoring Program RETS Radiological Effluent Technical Specifications RMS Records Management System RSZ Ramapo Seismic Zone RV Relief Valve RVT Random Vibration Theory SA Self Actuated SAR Safety Analysis Report SARA Superfund Amendments and Reauthorization Act SCDOT South Carolina Department of Transportation SCR Stable Continental Region SDWIS Safe Drinking Water Information System SECPOP Sector Population Land Fraction, and Economic Estimation Program SEUSSN Southeastern U.S. Seismic Network SGA Salisbury Geophysical Anomaly SLOSH Sea, Lake, and Overland Surges from Hurricanes SOV SolenoidOperated Valve SPH Standard Project Hurricane SPT Standard Penetration Test SSE Safe Shutdown Earthquake SSI SoilStructure Interaction SSSI StructureSoilSturcture Interaction STEL ShortTerm Exposure Limit TEDE Total Effective Dose Equivalent TIP Trial Implementation Project TLD Thermoluminescent Dosimeter TNT Trinitrotoluene TOC Top of Concrete TRT Test Review Team TSU Tsunami Model TWA Time Weighted Average UB Upper Bound UCSS Updated Charleston Seismic Source UFL Upper Flammability Limit UFSAR Updated Final Safety Analysis Report CCNPP Unit 3 1-11 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 Introduction Table 1.1-1— {Acronyms Used in this Document} (Page 6 of 6) Acronym Description UHS Uniform Hazard Spectra or Ultimate Heat Sink UHS MWIS Ultimate Heat Sink Makeup Water Intake Structure USACE U.S. Army Corps of Engineers USCG United States Coast Guard USCS Unified Sort Classification System USGS U.S. Geological Survey USNSN U.S. National Seismograph Network VA Virginia Vp Compressional Wave Velocity Vs ShearWave Velocity WOH Weight of Hammer WOR Weight of Rod WUS Western United States CCNPP Unit 3 1-12 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 Introduction Figure 1.1-1— {50 mi (80 km) Surrounding Area} FSAR: Chapter 1.0 CCNPP Unit 3 1-13 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 Introduction Figure 1.1-2— {10 mi (16 km) Surrounding Area} FSAR: Chapter 1.0 CCNPP Unit 3 1-14 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 Introduction Figure 1.1-3— {Site Area Map} FSAR: Chapter 1.0 CCNPP Unit 3 1-15 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 1.2 General Plant Description GENERAL PLANT DESCRIPTION This section of the U.S. EPR FSAR is incorporated by reference with the following supplements. The U.S. EPR FSAR includes the following COL Item in Section 1.2: A COL applicant that references the U.S. EPR design certification will identify those sitespecific features of the plant likely to be of special interest because of their relationship to safety. The COL applicant will also highlight items such as unusual site characteristics, solutions to particularly difficult engineering, construction problems, and significant extrapolations in technology represented by the site specific design. This COL Item is addressed as follows: {There are no sitespecific features of the plant considered to be of special interest because of their relationship to safety. There are no unusual site characteristics, and no particularly difficult engineering or construction problems, and no significant extrapolations in technology represented by the site specific design.} 1.2.1 Principal Design Criteria, Operating Characteristics, and Safety Considerations No departures or supplements. 1.2.2 Site Description The U.S. EPR FSAR includes the following conceptual design information in Section 1.2.2 for the Turbine Building: Turbine Building – [[ Figures 1.228 through 1.248. ]] The above conceptual design information is addressed as follows: An Alstom turbine generator design has been selected. This is the reference design reflected in U.S. EPR FSAR Section 10.1, 10.2, and 10.4.7. Figures in Section 1.2 of the U.S. EPR FSAR are incorporated by reference. The U.S. EPR FSAR includes the following conceptual design information in Section 1.2.2 for the Access Building: Access Building – [[ Figures 1.250 through 1.258. ]] The above conceptual design information is addressed as follows: The reference Access Building shown in U.S. EPR FSAR Figures 1.250 through 1.258 is incorporated by reference. The U.S. EPR FSAR includes the following COL Item in Section 1.2.2: A COL applicant that references the U.S. EPR design certification will provide a sitespecific layout figure. This COL Item is addressed as follows: CCNPP Unit 3 1-16 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 General Plant Description {The site specific layout is presented in Figure 1.1-3 showing the CCNPP Unit 3 circulating water system cooling tower and intake structures on the Chesapeake Bay. An enlargement of the layout of the Nuclear and Turbine Building Islands is presented in Figure 1.2-1.} The U.S. EPR FSAR includes the following COL Item in Section 1.2.2: A COL applicant that references the U.S. EPR design certification will provide sitespecific general arrangement drawings for the Turbine Building and Access Building. This COL Item is addressed as follows: The reference plant Turbine Building and Access Building are utilized. The general arrangement drawings provided in the U.S. EPR FSAR are incorporated by reference as discussed above. 1.2.3 Plant Description 1.2.3.1 1.2.3.1.1 Introduction to the U.S. EPR Design and Building Arrangement Overview No departures or supplements. 1.2.3.1.2 Buildings and Arrangement The U.S. EPR FSAR includes the following conceptual design information in Section 1.2.3.1.2 for the Turbine Building: Physical separation also protects the [[Turbine Building and Switchgear Building. The Turbine Building houses the components of the steam condensate main feedwater cycle, including the turbinegenerator. This building is located in a radial position with respect to the Reactor Building, but is independent from the NI. The Turbine Building is further described in Section 3.7.2. The Switchgear Building, which contains the power supply, the instrumentation and controls (I&C) for the balance of plant, and the SBO diesel generators, is located next to the Turbine Building and is physically separate from the NI. The Switchgear Building is shown in Figure 1.21.]] The above conceptual design information is addressed as follows: The reference Turbine Building and Switchgear Building designs are utilized. The information as stated in the U.S. EPR FSAR is incorporated by reference. 1.2.3.2 Reactor Coolant System No departures or supplements. 1.2.3.3 Engineered Safety Features and Emergency Systems No departures or supplements. 1.2.3.4 Instrumentation and Control Systems No departures or supplements. CCNPP Unit 3 1-17 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 1.2.3.5 1.2.3.5.1 General Plant Description Electrical Systems General The U.S. EPR FSAR includes the following conceptual design information in Section 1.2.3.5.1: [[ For operational flexibility and reliability, the switchyard is configured in either a breakerandahalf or double breaker scheme. ]] The above conceptual design information is addressed as follows: {The CCNPP Unit 3 switchyard is configured in a breaker and a half arrangement.} 1.2.3.5.2 Offsite Power No departures or supplements. 1.2.3.5.3 Onsite Power System No departures or supplements. 1.2.3.6 Power Conversion Systems No departures or supplements. 1.2.3.7 Fuel Handling and Storage Systems No departures or supplements. 1.2.3.8 Cooling Water and Other Auxiliary Systems No departures or supplements. 1.2.3.9 Radioactive Waste Management Systems No departures or supplements. CCNPP Unit 3 1-18 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 General Plant Description Figure 1.2-1— {CCNPP Unit 3 Nuclear and Turbine Building Island Layout} FSAR: Chapter 1.0 CCNPP Unit 3 1-19 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 1.3 Comparisons with Similar Facility Designs COMPARISONS WITH SIMILAR FACILITY DESIGNS This section of the U.S. EPR FSAR is incorporated by reference. CCNPP Unit 3 1-20 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 1.4 Identification of Agents and Contractors IDENTIFICATION OF AGENTS AND CONTRACTORS This section of the U.S. EPR FSAR is incorporated by reference with the following supplements. 1.4.1 Applicant – Program Manager {Calvert Cliffs 3 Nuclear Project, LLC and UniStar Nuclear Operating Services, LLC are applying for a combined license for CCNPP Unit 3. The owner of the proposed project is Calvert Cliffs 3 Nuclear Project, LLC. The operator of the proposed project is UniStar Nuclear Operating Services, LLC. The contact with the NRC during the licensing process is UniStar Nuclear Energy, LLC. UniStar Nuclear Energy, LLC is discussed in Section 1.4.2. Sections 1.4.1.1 and 1.4.1.2 are added as supplements to the U.S. EPR FSAR. 1.4.1.1 Calvert Cliffs 3 Nuclear Project, LLC Calvert Cliffs 3 Nuclear Project, LLC is a limited liability company and is an indirect subsidiary (through UniStar Nuclear Holdings, LLC and UniStar Project Holdings, LLC, which operate as holding companies) of UniStar Nuclear Energy, LLC. UniStar Nuclear Energy is owned jointly by Constellation New Nuclear, LLC and by EDF, Inc. Constellation New Nuclear is a member (through Constellation Nuclear, LLC) of Constellation Energy Group, Inc. EDF Development is an indirect subsidiary of (through EDF International, SA) of Èlecticitè de Franco, SA. The principal offices of Calvert Cliffs 3 Nuclear Project, LLC are located in Baltimore, Maryland. Calvert Cliffs 3 Nuclear Project, LLC is organized under the laws of the State of Delaware pursuant to the Limited Liability Company Agreement of Calvert Cliffs 3 Nuclear Project, LLC dated March 10, 2008, by UniStar Project Holdings, LLC. Calvert Cliffs 3 Nuclear Project, LLC will be one of the licensees and will own CCNPP Unit 3. Constellation Energy Group is a holding company for several companies involved with electric and gas energy. Constellation Energy Group, through its subsidiaries, is a major generator of electric power and a leading supplier of competitive electricity, with a power generation portfolio of over 8,700 megawatts. The output of Constellation Energy Group’s plants is sold by Constellation Energy Group’s commodities business, Constellation Energy Commodities Group, Inc., to many of the nation’s leading distribution utilities, energy companies, and cooperatives. 1.4.1.2 UniStar Nuclear Operating Services, LLC UniStar Nuclear Operating Services, LLC has been formed to be a licensee and to operate U.S. EPR nuclear power plants in the United States. The principal offices of UniStar Nuclear Operating Services, LLC are located in Baltimore, Maryland. UniStar Nuclear Operating Services, LLC is organized under the laws of the State of Delaware pursuant to the entity’s articles of incorporation, dated May 12, 2006. This entity will be one of the licensees for, and will provide the operating services for, CCNPP Unit 3.} 1.4.2 Other Contractors and Participants The U.S. EPR FSAR includes the following COL Item in Section 1.4.2: A COL applicant that references the U.S. EPR design certification will identify the prime agents or contractors for the construction and operation of the nuclear power plant. CCNPP Unit 3 1-21 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 Identification of Agents and Contractors This COL Item is addressed as follows: Design responsibility for the U.S. EPR nuclear power plant resides with AREVA NP Inc. (AREVA NP) for the portions of the facility included in the design certification application. AREVA NP has headquarters in Lynchburg, Virginia, and major design organizations in Lynchburg, Virginia; Charlotte, North Carolina; and Marlborough, Massachusetts. AREVA NP is an AREVA and Siemens company. AREVA NP and its predecessor companies have designed light water reactors for over 40 years. As such, AREVA NP has extensive nuclear design experience in addition to maintaining fabrication facilities for fuel and major components in Europe and the United States. AREVA NP will provide additional services during conduct of startup testing. {Bechtel North American Power Corporation (Bechtel) provides design services for portions of the facility design not included in the U.S. EPR design certification (balance of plant) and is expected to be the prime contractor for the construction of CCNPP Unit 3. Bechtel has extensive architecturalengineering experience, and has participated in the design and construction of more than 150 nuclear power plants worldwide. Bechtel provides design assistance to AREVA NP which retains design responsibility for the U.S. EPR. UniStar Nuclear Energy, LLC. provides project management, engineering, procurement, training, regulatory affairs and startup, testing, and commissioning support during the design, construction, startup and operation of CCNPP Unit 3. CCNPP Unit 3 will be operated by UniStar Nuclear Operating Services, LLC as discussed in Section 1.4.1.2.} Other various agents and contractors provide specialized services to the project. CCNPP Unit 3 1-22 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 1.5 Requirements for Further Technical Information REQUIREMENTS FOR FURTHER TECHNICAL INFORMATION This section of the U.S. EPR FSAR is incorporated by reference. CCNPP Unit 3 1-23 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 1.6 Material Referenced MATERIAL REFERENCED This section of the U.S. EPR FSAR is incorporated by reference with the following supplements. The U.S. EPR FSAR includes the following COL Item in Section 1.6: A COL applicant that references the U.S. EPR design certification will include any sitespecific topical reports that are incorporated by reference as part of the COL application in Table 1.6-1. This COL Item is addressed as follows: Table 1.6-1 of this FSAR contains a list of topical reports submitted to the NRC to support this application. CCNPP Unit 3 1-24 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 Material Referenced Table 1.6-1— {Reports Referenced} Report No. Title/Revision Date Submitted to the NRC FSAR Section NEI 0708A Generic FSAR Template Guidance for Ensuring that Occupational Radiation Exposures Are As Low As Is Reasonably Achievable (ALARA), Revision 0 October 2009 12.1.3 NEI 0703A Generic FSAR Template Guidance for Radiation Protection Program Description, Revision 0 May 2009 12.1.3 12.5 NEI 0613A Template for an Industry Training Program Description, Revision 2 March 2009 13.2 UNTR06001A Quality Assurance Program Description, Revision 0 April 2007 17.5 NEI 0702A Generic FSAR Template Guidance for Maintenance Rule Program Description for Plants Licensed Under 10 CFR Part 52, Revision 0 March 2008 17.7 NEI 0606 Fitness for Duty Program Guidance for New Revision Power Plant Construction Sites, Revision 5 August 2009 13.7 NEI 0407 Pressurized Water Reactor Sump Performance Evaluation Methodology December 2004 6.3.2.2.2 NEI 0002 Probabilistic Risk Assessment (PRA) Peer Review Process Guidance, Revision 1 May 2006 19.1.2 NEI 0709A Generic FSAR Template Guidance for Offsite Dose Calculation Manual (ODCM) Description, Revision 0 March 2009 11.5 NEI 0710A Generic FSAR Template Guidance for Process Control Program (PCP), Revision 0 August 2009 11.4 NEI 0808A Generic FSAR Template Guidance for Life Cycle Minimization of Contamination October 2009 11.2,11.3,11.4,11.5 CCNPP Unit 3 1-25 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 1.7 Drawings and Other Detailed Information DRAWINGS AND OTHER DETAILED INFORMATION This section of the U.S. EPR FSAR is incorporated by reference with the following supplements. 1.7.1 Electrical and Instrumentation and Control Drawings The U.S. EPR FSAR includes the following COL Item in Section 1.7.1: A COL applicant that references the U.S. EPR design certification will list additional site specific instrumentation and control functional diagrams and electrical oneline diagrams included in the COL FSAR in Table 1.7-1 and supplement the figure legends, if applicable. This COL Item is addressed as follows: Table 1.7-1 contains a list of site specific instrumentation and control functional diagrams and electrical oneline diagrams included in the COL FSAR. 1.7.2 Piping and Instrumentation Diagrams The U.S. EPR FSAR includes the following COL Item in Section 1.7.2: A COL applicant that references the U.S. EPR design certification will list additional site specific P&IDs included in the COL FSAR in Table 1.7-2 and supplement the figure legend, if applicable. This COL Item is addressed as follows: A list of site specific P&IDs included in the {CCNPP Unit 3} FSAR is presented in Table 1.72. CCNPP Unit 3 1-26 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 Drawings and Other Detailed Information Table 1.7-1— {I&C Functional and Electrical One Line Diagrams} FSAR Figure Number Title Figure 8.2-2 CCNPP Unit 3 500 kv Switchyard Single Line Diagram Figure 8.3-1 CCNPP Unit 3 Emergency Power Supply System Single Line Drawing (three sheets) Figure 8.3-2 CCNPP Unit 3 Normal Power Supply System Single Line Drawing (five sheets) Figure 8.3-3 CCNPP Unit 3 Transformer 30BBT03 Distribution System Single Line Drawing CCNPP Unit 3 1-27 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 Drawings and Other Detailed Information Table 1.7-2— {Piping and Instrumentation Diagrams} FSAR Figure Number Title Figure 9.2-1 Potable Water System Figure 9.2-2 Sanitary Waste Water System Figure 9.2-3 Normal Makeup, Ultimate Heat Sink Makeup, Blowdown & Chemical Treatment Figure 9.2-7 Raw Water & Desalinated Water Supply Figure 9.4-1 Turbine Building Ventilation System Figure 9.4-2 UHS Makeup Water Intake Structure Ventilation System Figure 9.5-1 CCNPP Unit 3 Fire Water Distribution System Cooling Tower Loop Figure 9.5-2 CCNPP Unit 3 Fire Water Distribution System Intake Structure Loop Figure 9.5-3 CCNPP Unit 3 UHS Makeup Water Intake Structure Figure 10.4-1 Circulating Water System P& ID (Circulating Water Pump Building) Figure 10.4-2 Circulating Water System P& ID (Turbine Building) Figure 10.4-3 Circulating Water System Makeup System P& ID Figure 10.4-6 Circulating Water System Blowdown Flowpath CCNPP Unit 3 1-28 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 1.8 Interfaces with Standard Designs and Early Site Permits INTERFACES WITH STANDARD DESIGNS AND EARLY SITE PERMITS This section of the U.S. EPR FSAR is incorporated by reference with the following supplements. The U.S. EPR FSAR includes the following COL Item in Section 1.8: A COL applicant that references the U.S. EPR design certification will describe where the interface requirements are satisfied in the COL Final Safety Analysis Report (FSAR) to demonstrate compatibility with the U.S. EPR design. This COL Item is addressed as follows: Interface requirements for systems, structures, and components (SSCs) that relate to specific mechanical, electrical, nuclear, or structural systems are identified in appropriate sections of the FSAR. Table 1.8-1 provides a crossreference to the description of these interfaces. 1.8.1 COL Information Items The U.S. EPR FSAR includes the following COL Item in Section 1.8.1: A COL applicant that references the U. S. EPR design certification will identify the FSAR section, or provide a list, that demonstrates how the COL information items have been addressed. This COL Item is addressed as follows: The text of the COL Items and COL No. identifier listed in Table 1.82 of the U.S. EPR FSAR are presented in Table 1.8-2. For each COL Item listed, the corresponding section of this FSAR that addresses the COL Item is identified. Additional explanatory comments are provided as necessary or appropriate. CCNPP Unit 3 1-29 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 1.8.2 Interfaces with Standard Designs and Early Site Permits Departures The U.S. EPR FSAR includes the following COL Item in Section 1.8.2: A COL applicant that references the U. S. EPR design certification will provide a list of any departures from the FSAR in the COL FSAR. This COL Item is addressed as follows: {The list of departures from the U.S. EPR FSAR is as follows: Maximum Differential Settlement (across the basemat) Maximum Annual Average Atmospheric Dispersion Factor (0.5 mile limiting sector) Accident Atmospheric Dispersion Factor from (0 2 hour, Low Population Zone, 1.5 miles) InStructure Response Spectra Toxic Gas Detection and Isolation Minimum Shear Wave Velocity Maximum NonCoincident Wet Bulb Temperature Value at 0% Exceedance (85°F) Coefficient of Static Friction Generic Technical Specifications and Bases Setpoint Control Program FSAR 2.5.4 and 3.8.5 FSAR 2.3.5 FSAR 2.3.4 and 15.0.3 FSAR 3.7.2.5.2 FSAR 3.11, 6.4, 9.4.1 and 14.2.12 FSAR 2.5.4.2.5.8 and COLA Part 10, ITAAC Table 2.41 FSAR 2.0, 2.3, and 9.2.1 FSAR 3.8.5.5 FSAR 16 (COLA Part 4) Justification for these departures is presented in Part 7 of the COL application.} CCNPP Unit 3 1-30 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 Interfaces with Standard Designs and Early Site Permits Table 1.8-1— FSAR Sections that Demonstrate Conformance to U.S. EPR FSAR Interface Requirements Item No. Interface Interface Type FSAR Section 11 Switchgear Building U.S. EPR Interface 1.2, 8.3, 8.4 12 Access Building U.S. EPR Interface 1.2, 3.7.2 13 Turbine Building U.S. EPR Interface 1.2, 3.7.2 14 Fire Protection Storage Tanks and Building U.S. EPR Interface 1.2, 3.7.2 21 Envelope of U.S. EPR site related design Site Parameter 2.0, Table 2.0-1 22 Consequences of potential hazards from nearby industrial, transportation and military facilities Site Parameter 2.2 23 Sitespecific χ/Q values based on sitespecific meteorological data at the exclusion area boundary (EAB), low population zone (LPZ), and control room Site Parameter 2.3 24 Sitespecific seismic characteristics Site Parameter 2.5, 3.7 25 Soil conditions and profiles Site Parameter 2.5 26 Bearing pressure of soil beneath the nuclear island basemat Site Parameter 2.5 27 Foundation settlements Site Parameter 2.5 31 Missiles generated from nearby facilities Site Parameter 3.5 32 Missiles generated by tornadoes or extreme winds Site Parameter 3.5 33 Aircraft hazards Site Parameter 3.5 34 Sitespecific loads that lie within the standard plant design envelope for Seismic Category I structures Site Parameter 3.8 35 Buried conduit and duct banks, and pipe and pipe ducts U.S. EPR Interface 3.8 81 Offsite AC power transmission system connections to the switchyard and the connection to the plant power distribution system U.S. EPR Interface 8.2 82 Onsite AC power transmission system connections to the switchyard and the connection to the plant power distribution system U.S. EPR Interface 8.3 83 Auxiliary power and generator transformer areas U.S. EPR Interface 8.2 84 Lightning protection and grounding system grid U.S. EPR Interface 8.3.1 92 Provide support systems such as makeup water, blowdown and chemical treatment (to control biofouling) for the UHS U.S. EPR Interface 9.2.5 93 Raw water system U.S. EPR Interface 9.2.9 94 Fire water distribution system U.S. EPR Interface 9.5.1 101 Design details for circulating water system including makeup water, and water treatment U.S. EPR Interface 10.4.5 111 Process Control program and program aspects of process and effluent monitoring and sampling U.S. EPR Interface 11.5 131 Sitespecific information for administrative, operating, emergency, maintenance, and other operating procedures. U.S. EPR Interface 13.5 132 Sitespecific emergency plan U.S. EPR Interface 13.3 133 Sitespecific security assessment and Physical Security Plan U.S. EPR Interface 13.6 141 Sitespecific information for development of the initial test program U.S. EPR Interface 14.2 CCNPP Unit 3 1-31 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 Interfaces with Standard Designs and Early Site Permits Table 1.8-2— FSAR Sections that Address COL Items (Page 1 of 20) Item No. Description Section 1.11 A COL applicant that references the U.S. EPR design certification and proposes a multiunit license application will provide the changes and additional information needed to license a multiunit plant. 1.12 A COL applicant that references the U.S. EPR design certification will identify the specific plant site location. 1.1.1 1.13 A COL applicant that references the U.S. EPR design certification will provide the estimated schedules for completion of construction and commercial operation. 1.1.5 1.21 A COL applicant that references the U.S. EPR design certification will identify those site specific features of the plant likely to be of special interest because of their relationship to safety. The COL applicant will also highlight items such as unusual site characteristics, solutions to particularly difficult engineering, construction problems, and significant extrapolations in technology represented by the site specific design. 1.22 A COL applicant that references the U.S. EPR design certification will provide a sitespecific layout figure. 1.2.2 1.23 A COL applicant that references the U.S. EPR design certification will provide sitespecific general arrangement drawings for the Turbine Building and Access Building. 1.2.2 1.41 A COL applicant that references the U.S. EPR design certification will identify the prime agents or contractors for the construction and operation of the nuclear power plant. 1.4.2 1.61 A COL applicant that references the U.S. EPR design certification will include any sitespecific topical reports that are incorporated by reference as part of the COL application in Table 1.6-1. 1.71 A COL applicant that references the U.S. EPR design certification will list additional site specific instrumentation and control functional diagrams and electrical oneline diagrams included in the COL FSAR in Table 1.7-1 and supplement the figure legends, if applicable. 1.7.1 1.72 A COL applicant that references the U.S. EPR design certification will list additional site specific P&IDs included in the COL FSAR in Table 1.7-2 and supplement the figure legend, if applicable. 1.7.2 1.81 A COL applicant that references the U.S. EPR design certification will describe where the interface requirements are satisfied in the COL FSAR to demonstrate compatibility with the U.S. EPR design. 1.8 1.82 A COL applicant that references the U. S. EPR design certification will identify the FSAR section, or provide a list, that demonstrates how the COL information items have been addressed. 1.8.1 1.83 A COL applicant that references the U. S. EPR design certification will provide a list of any departures from the FSAR in the COL FSAR. 1.8.2 1.91 A COL applicant that references the U.S. EPR design certification will review and address the conformance with Regulatory Criteria in effect six months before the docket date of the COL application for the sitespecific portions and operational aspects of the facility design. 1.9 2.01 A COL applicant that references the U.S. EPR design certification will compare the characteristics of its proposed site to the site parameters in Table 2.11. If the characteristics of the site fall within the assumed site parameters in Table 2.11, then the U.S. EPR standard design is bounding for the site. For sitespecific characteristics that are outside the bounds of the assumptions presented in Table 2.11, the COL applicant will demonstrate that the U.S. EPR design acceptably meets the regulatory requirements, given the more limiting sitespecific characteristic. In such an instance, the COL applicant will also demonstrate that the design commitments and acceptance criteria described in the FSAR do not need to be changed, or will propose new design commitments or acceptance criteria, or both. 2.0 2.11 A COL applicant that references the U.S. EPR design certification will provide sitespecific information related to site location and description, exclusion area authority and control, and population distribution. 2.1 2.21 A COL applicant that references the U.S. EPR design certification will provide sitespecific information related to the identification of potential hazards stemming from nearby industrial, transportation, and military facilities within the site vicinity, including an evaluation of potential accidents (such as explosions, toxic chemicals, and fires). 2.2 CCNPP Unit 3 1-32 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED 1.1 1.2 1.6 Rev. 7 FSAR: Chapter 1.0 Interfaces with Standard Designs and Early Site Permits Table 1.8-2— FSAR Sections that Address COL Items (Page 2 of 20) Item No. Description Section 2.22 A COL applicant that references the U.S. EPR design certification will provide information concerning sitespecific evaluations to determine the consequences that potential accidents at nearby industrial, transportation, and military facilities could have on the site. The information provided by the COL applicant will include specific changes made to the U.S. EPR design to qualify the design of the site against potential external accidents with an unacceptable probability of severe consequences. 2.2.3 2.31 If A COL applicant that references the U.S. EPR design certification identifies sitespecific meteorology values outside the range of the site parameters in Table 2.11, then the COL applicant will demonstrate the acceptability of the sitespecific values in the appropriate sections of the Combined License application. 2.3 2.32 A COL applicant that references the U.S. EPR design certification will provide sitespecific characteristics for regional climatology. 2.3.1 2.33 A COL applicant that references the U.S. EPR design certification will provide sitespecific characteristics for local meteorology. 2.3.2 2.34 A COL applicant that references the U.S. EPR design certification will provide the sitespecific, onsite meteorological measurement program. 2.3.3 2.35 A COL applicant that references the U.S. EPR design certification will provide a description of the atmospheric dispersion modeling used in evaluating potential design basis events to calculate concentrations of hazardous materials (e.g., flammable or toxic clouds) outside building structures resulting from the onsite and/or offsite airborne releases of such materials. 2.3.4 2.36 A COL applicant that references the U.S. EPR design certification will confirm that site specific χ/Q values, based on sitespecific meteorological data, are bounded by those specified in Table 2.11 at the EAB, LPZ and at the control room. For sitespecific χ/Q values that exceed the bounding χ/Q values, a COL applicant that references the U.S. EPR design certification will demonstrate that the radiological consequences associated with the controlling design basis accident continue to meet the dose reference values given in 10 CFR 50.34 and the control room operator dose limits given in GDC 19 using sitespecific χ/Q values. 2.37 A COL applicant that references the U.S. EPR design will provide χ/Q values for each cumulative frequency distribution which exceeds the median value (50 percent of the time) as part of the assessment of the postulated impact of an accident on the environment. 2.38 A COL applicant that references the U.S. EPR design certification will provide the sitespecific, longterm diffusion estimates for routine releases. In developing this information, the COL applicant should consider the guidance provided in RG 1.23, RG 1.109, RG 1.111, and RG 1.112. 2.3.5 2.39 A COL applicant that references the U.S EPR design certification will also provide estimates of annual average atmospheric dispersion (χ/Q values) and deposition (D/Q values) for 16 radial sectors to a distance of 50 miles (80 km) from the plant as part of its environmental assessment. 2.3.5 2.310 A COL applicant that references the U.S. EPR design certification will describe the means for providing UHS makeup sufficient to meet the maximum evaporative and drift water loss after 72 hours through the remainder of the 30 day period consistent with RG 1.27. 2.3.1.2 2.41 A COL applicant that references the U.S. EPR design certification will provide a sitespecific description of the hydrologic characteristics of the plant site. 2.4.1 2.42 A COL applicant that references the U.S. EPR design certification will identify sitespecific information related to flood history, flood design considerations, and effects of local intense precipitation. 2.4.2 2.43 A COL applicant that references the U.S. EPR design certification will provide sitespecific information to describe the probable maximum flood of streams and rivers and the effect of flooding on the design. 2.4.3 2.44 A COL applicant that references the U.S. EPR design certification will verify that the site specific potential hazards to the safetyrelated facilities due to the failure of upstream and downstream water control structures are within the hydrogeologic design basis. 2.4.4 CCNPP Unit 3 1-33 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED 2.3.4.2 2.3.4.2.2 Rev. 7 FSAR: Chapter 1.0 Interfaces with Standard Designs and Early Site Permits Table 1.8-2— FSAR Sections that Address COL Items (Page 3 of 20) Item No. Description Section 2.45 A COL applicant that references the U.S. EPR design certification will provide sitespecific information on the probable maximum surge and seiche flooding and determine the extent to which safetyrelated plant systems require protection. The applicant will also verify that the sitespecific characteristic envelope is within the design maximum flood level, including consideration of wind effects. 2.4.5 2.46 A COL applicant that references the U.S. EPR design will provide sitespecific information and determine the extent to which safetyrelated facilities require protection from tsunami effects, including Probable Maximum Tsunami Flooding. 2.4.6 2.47 A COL applicant that references the U.S. EPR design certification will provide sitespecific information regarding ice effects and design criteria for protecting safetyrelated facilities from iceproduced effects and forces with respect to adjacent water bodies. 2.4.7 2.48 A COL applicant that references the U.S. EPR design certification will evaluate the potential for freezing temperatures that may affect the performance of the ultimate heat sink makeup, including the potential for frazil and anchor ice, maximum ice thickness, and maximum cumulative degreedays below freezing. 2.4.7 2.49 A COL applicant that references the U.S. EPR design certification will provide sitespecific information and describe the design basis for cooling water canals and reservoirs used for makeup to the UHS cooling tower basins. 2.4.8 2.410 A COL applicant that references the U.S. EPR design certification will provide sitespecific information and demonstrate that in the event of diversion or rerouting of the source of cooling water, alternate water supplies will be available to safetyrelated equipment. 2.4.9 2.411 A COL applicant that references the U.S. EPR design certification will use sitespecific information to compare the location and elevations of safetyrelated facilities, and of structures and components required for protection of safetyrelated facilities, with the estimated static and dynamic effects of the design basis flood conditions. 2.4.10 2.412 A COL applicant that references the U.S. EPR design certification will identify natural events that may reduce or limit the available cooling water supply, and will verify that an adequate water supply exists for operation or shutdown of the plant in normal operation, anticipated operational occurrences, and in low water conditions. 2.4.11 2.413 A COL applicant that references the U.S. EPR design certification will provide sitespecific information to identify local and regional groundwater reservoirs, subsurface pathways, onsite use, monitoring or safeguard measures, and to establish the effects of groundwater on plant structures. 2.4.12 2.414 A COL applicant that references the U.S. EPR design certification will provide sitespecific information on the ability of the groundwater and surface water environment to delay, disperse, dilute, or concentrate accidental radioactive liquid effluent releases, regarding the effects that such releases might have on existing and known future uses of groundwater and surface water resources. 2.4.13 2.415 A COL applicant that references the U.S. EPR design certification will describe any emergency measures required to implement flood protection in safetyrelated facilities and to verify there is an adequate water supply for shutdown purposes. 2.4.14 2.51 A COL applicant that references the U.S. EPR design certification will use sitespecific information to investigate and provide data concerning geological, seismic, geophysical, and geotechnical information. 2.5.1 2.52 A COL applicant that references the U.S. EPR design certification will review and investigate sitespecific details of seismic, geophysical, geological, and geotechnical information to determine the safe shutdown earthquake (SSE) ground motion for the site and compare site specific ground motion to the Certified Seismic Design Response Spectra (CSDRS) for the U.S. EPR. 2.5.2 2.53 A COL applicant that references the U.S. EPR design certification will compare the final sitespecific soil characteristics with the U.S. EPR design generic soil parameters and verify that the sitespecific seismic characteristics are enveloped by the CSDRS (anchored at 0.3 g PGA) and the 10 generic soil profiles discussed in Section 2.5.2, 2.5.4.7 and 3.7.1 and summarized in Table 3.7.16. 2.5.2.6 CCNPP Unit 3 1-34 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 Interfaces with Standard Designs and Early Site Permits Table 1.8-2— FSAR Sections that Address COL Items (Page 4 of 20) Item No. Description Section 2.54 A COL applicant that references the U.S. EPR design certification will verify that sitespecific foundation soils beneath the foundation basemats of Seismic Category I structures have the capacity to support the bearing pressure with a factor of safety of 3.0 under static conditions. 2.5.4.10.1 2.55 A COL applicant that references the U.S. EPR design certification will investigate sitespecific surface and subsurface geologic, seismic, geophysical, and geotechnical aspects within 25 miles around the site and evaluate any impact to the design. The COL applicant will demonstrate that no capable faults exist at the site in accordance with the requirements of 10 CFR 100.23 and of 10 CFR 50, Appendix S. If noncapable surface faulting is present under foundations for safetyrelated structures, the COL applicant will demonstrate that the faults have no significant impact on the structural integrity of safetyrelated structures, systems, or components. 2.5.3 2.56 A COL applicant that references the U.S. EPR design certification will present sitespecific information about the properties and stability of soils and rocks that may affect the nuclear power plant facilities under both static and dynamic conditions, including the vibratory ground motions associated with the CSDRS and the site specific SSE. 2.5.4 2.57 A COL applicant that references the U.S. EPR design certification will verify that the predicted differential settlement value of ½ in per 50 ft in any direction across the foundation basemat of a Seismic Category I structure is not exceeded. Settlement values larger than this may be demonstrated acceptable by performing additional sitespecific evaluations. 2.5.4.10.2 2.58 A COL applicant that references the U.S. EPR design certification will evaluate sitespecific information concerning the stability of earth and rock slopes, both natural and manmade (e.g., cuts, fill, embankments, dams, etc.), of which failure could adversely affect the safety of the plant. 2.5.5 2.59 A COL applicant that references the U.S. EPR design certification will reconcile the site specific soil properties with those used for design of U.S. EPR Seismic Category I structures and foundations described in Section 3.8. 2.510 A COL applicant that references the U.S. EPR design certification will investigate and determine the uniformity of the underlying layers of site specific soil conditions beneath the foundation basemats. The classification of uniformity or nonuniformity will be established by a geotechnical engineer. 2.5.4.10.3 3.11 A COL applicant that references the U.S. EPR design certification will identify the sitespecific QA Program Plan that demonstrates compliance with GDC1. 3.1.1.1.1 3.21 A COL applicant that references the U.S. EPR design certification will identify the seismic classification of applicable sitespecific SSCs that are not identified in Table 3.2.21. 3.2.1 3.22 A COL applicant that references the U.S. EPR design certification will identify the quality group classification of applicable sitespecific SSCs important to safety that are not identified in Table 3.2.21. 3.2.2 3.31 A COL applicant that references the U.S. EPR design certification will determine sitespecific wind and tornado characteristics and compare these to the standard plant criteria. If the sitespecific wind and tornado charactistics are not bounded by the site parameters, postulated for the certified design, then the COL applicant will evaluate the design for sitespecific wind and tornado events and demonstrate that these loadings will not adversely affect the ability of safetyrelated structures to perform their safety functions during or after such events. 3.3 3.32 A COL applicant that references the U.S. EPR design certification will demonstrate that failure of sitespecific structures or components not included in the U.S. EPR standard plant design, and not designed for wind loads, will not affect the ability of other structures to perform their intended safety functions. 3.3.1 3.33 A COL applicant that references the U.S. EPR design certification will demonstrate that failure of sitespecific structures or components not included in the U.S. EPR standard plant design, and not designed for tornado loads, will not affect the ability of other structures to perform their intended safety functions. 3.3.2 3.41 A COL applicant that references the U.S. EPR design certification will confirm the potential site specific external flooding events are bounded by the U.S. EPR design basis flood values or otherwise demonstrate that the design is acceptable. CCNPP Unit 3 1-35 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED 2.5.4.2 3.4.3.2 Rev. 7 FSAR: Chapter 1.0 Interfaces with Standard Designs and Early Site Permits Table 1.8-2— FSAR Sections that Address COL Items (Page 5 of 20) Item No. Description Section 3.42 A COL applicant that references the U.S. EPR design certification will perform a flooding analysis for the ultimate heat sink makeup water intake structure based on the sitespecific design of the structures and the flood protection concepts provided herein. 3.4.3.10 3.43 A COL applicant that references the U.S. EPR design certification will define the need for a sitespecific permanent dewatering system. 3.4.3.11 3.44 A COL applicant that references the U.S. EPR design certification will perform internal flooding analyses prior to fuel load for the Safeguard Buildings and Fuel Building to demonstrate that the impact of internal flooding is contained within the Safeguard Building or Fuel Building division of origin. 3.4.1 3.45 A COL applicant that references the U.S. EPR design certification will perform an internal flooding analysis prior to fuel load for the Reactor Building and Reactor Building Annulus to demonstrate that the essential equipment required for safe shutdown is located above the internal flood level. 3.4.1 3.46 A COL applicant that references the U.S. EPR design certification will include in its maintenance program appropriate watertight door preventive maintenance in accordance with manufacturer recommendations so that each Safeguards Building watertight door above elevation +0 feet remains capable of performing its intended function. 3.4.1 3.47 A COL applicant that references the U.S. EPR design certification will design the watertight seal between the Access Building and the adjacent Category I access path to the Reactor Building Tendon Gallery. Watertight seal design will account for hydrostatic loads, lateral earth pressure loads, and other applicable loads. 3.4.2 3.51 A COL applicant that references the U.S. EPR design certification will describe controls to confirm that unsecured maintenance equipment, including that required for maintenance and that are undergoing maintenance, will be removed from containment prior to operation, moved to a location where it is not a potential hazard to SSCs important to safety, or seismically restrained to prevent it from becoming a missile. 3.5.1.2.3 3.52 A COL applicant that references the U.S. EPR design certification will confirm the evaluation of the probability of turbine missile generation for the selected turbine generator, P1, is less than 1 x 104 for turbinegenerators favorably oriented with respect to containment. 3.5.1.3 3.53 A COL applicant that references the U.S. EPR design certification will assess the effect of potential turbine missiles from turbine generators within other nearby or colocated facilities. 3.5.1.3 3.54 A COL applicant that references the U.S. EPR design certification will evaluate the potential for other missiles generated by natural phenomena, such as hurricanes and extreme winds, and their potential impact on the missile protection design features of the U.S. EPR. 3.5.1.4 3.55 A COL applicant that references the U.S. EPR design certification will evaluate the potential for site proximity explosions and missiles generated by these explosions for their potential impact on missile protection design features. 3.5.1.5 3.56 A COL applicant that references the U.S. EPR design certification will evaluate sitespecific aircraft hazards and their potential impact on plant SSCs. 3.5.1.6 3.57 For sites with surrounding ground elevations higher than plant grade, a COL applicant that references the U.S. EPR design certification will confirm that automobile missiles cannot be generated within a 0.5 mile radius of safetyrelated SSCs that would lead to impact higher than 30 ft above plant grade. 3.5.1.4 3.58 A COL applicant that references the U.S. EPR design certification will describe controls to confirm that unsecured compressed gas cylinders will be either removed or seismically supported when not in use to prevent them from becoming missiles. 3.5.1.1.3 3.59 A COL applicant that references the U.S. EPR design certification will describe controls to confirm that unsecured maintenance equipment, including that required for maintenance and that are undergoing maintenance, will be either removed or seismically supported when not in use to prevent it from becoming a missile. 3.5.1.1.3 3.61 A COL applicant that references the U.S. EPR design certification will perform the pipe break hazards analysis and reconcile deviations in the asbuilt configuration to the asdesigned analysis. CCNPP Unit 3 1-36 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED 3.6.1 Rev. 7 FSAR: Chapter 1.0 Interfaces with Standard Designs and Early Site Permits Table 1.8-2— FSAR Sections that Address COL Items (Page 6 of 20) Item No. Description Section 3.62 A COL applicant that references the U.S. EPR design certification will perform the pipe break hazards analysis and reconcile deviations in the asbuilt configuration to the asdesigned analysis. 3.6.2.1 3.63 A COL applicant that references the U.S. EPR design certification will confirm that the design LBB analysis remains bounding for each piping system and provide a summary of the results of the actual asbuilt plant specific LBB analysis, including material properties of piping and welds, stress analyses, leakage detection capability, and degradation mechanisms. 3.6.3 3.64 A COL applicant that references the U.S. design certification will provide diagrams showing the final asdesigned configurations, locations, and orientations of the pipe whip restraints in relation to break locations in each piping system. 3.6.2.5.1 3.65 A COL applicant that references the U.S. EPR design certification will implement the ISI program as augmented with NRC approved ASME Code cases that are developed and approved for augmented inspections of Alloy 690/152/52 material to address PWSCC concerns. 3.6.3 3.71 A COL applicant that references the U.S. EPR design certification will confirm that the site specific seismic response is within the parameters of section 3.7 of the U.S. EPR standard design. 3.7.2 3.72 A COL applicant that references the US EPR design certification will provide the sitespecific separation distances for the access building and turbine building. 3.7.2.8 3.73 A COL applicant that references the U.S. EPR design certification will provide a description of methods used for seismic analysis of sitespecific Category I concrete dams, if applicable. 3.7.3.13 3.74 A COL applicant that references the U.S. EPR design certification will determine whether essentially the same seismic response from a given earthquake is expected at each of the units in a multiunit site or instrument each unit. In the event that only one unit is instrumented, annunciation shall be provided to each control room. 3.7.4.2 3.75 A COL applicant that references the U.S. EPR design certification will determine a location for the freefield acceleration sensor such that the effects associated with surface features, buildings, and components on the recordings of ground motion are insignificant. The acceleration sensor must be based on material representative of that upon which the Nuclear Island (NI) and other Seismic Category I structures are founded. 3.7.4.2.1 3.76 A COL applicant that references the US EPR design certification will provide the seismic design basis for the sources of fire protection water supply for safe plant shutdown in the event of a SSE. 3.7.2.8 3.77 A COL applicant that references the U.S. EPR design certification will demonstrate that the response of the Access Building to an SSE event will not impair the ability of Seismic Category I systems, structures, or components to perform their design basis safety functions. 3.7.2.8 3.78 A COL applicant that references the U.S. EPR design certification will demonstrate that the response of the TB (including Switchgear Building on the common basemat) to an SSE event will not impair the ability of Seismic Category I systems, structures, or components to perform their design basis safety functions. 3.7.2.8 3.81 A COL applicant that references the U.S. EPR design certification will confirm that site specific loads lie within the standard plant design envelope for the Reactor Containment Building, or perform additional analyses to verify structural adequacy. 3.8.1.3 3.82 A COL applicant that references the U.S. EPR design certification will describe any differences between the standard plant layout and design of Seismic Category I structures required for sitespecific conditions. 3.8.4.1 3.83 A COL applicant that references the U.S. EPR design certification will confirm that site specific loads lie within the standard design envelope for other Seismic Category I structures, or perform additional analyses to verify structural adequacy. 3.8.4.3 3.84 A COL applicant that references the U.S. EPR design certification will provide a description of Seismic Category I buried conduit and duct banks. 3.8.4.1.8 3.85 A COL applicant that references the U.S. EPR design certification will provide a description of Seismic Category I buried pipe and pipe ducts. 3.8.4.1.9 CCNPP Unit 3 1-37 © 2007-2010 UniStar Nuclear Services, LLC. 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COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 Interfaces with Standard Designs and Early Site Permits Table 1.8-2— FSAR Sections that Address COL Items (Page 7 of 20) Item No. Description Section 3.86 A COL applicant that references the U.S. EPR design certification will confirm that site specific loads lie within the standard design envelope for RB internal structures, or perform additional analyses to verify structural adequacy. 3.8.3.3 3.87 A COL applicant that references the U.S. EPR design certification will confirm that sitespecific conditions for Seismic Category I buried conduit, electrical duct banks, pipe, and pipe ducts satisfy the requirements specified in Section 3.8.4.4.5 and those specified in AREVA NP Topical Report ANP10264NPA. 3.8.4.5 3.88 A COL applicant that references the U.S. EPR design certification will address sitespecific Seismic Category I structures that are not described in this section. 3.8.4.1 3.89 A COL applicant that references the U.S. EPR design certification will describe sitespecific foundations for Seismic Category I structures that are not described in this section. 3.8.5.1 3.810 A COL applicant that references the U.S. EPR design certification will evaluate sitespecific methods for shear transfer between the foundation basemats and underlying soil for sitespecific soil characteristics that are not within the envelope of the soil parameters specified in Section 2.5.4.2. 3.8.5.5 3.811 A COL applicant that references the U.S. EPR design certification will evaluate the use of epoxy coated rebar for foundations subjected to aggressive environments, as defined in ACI 34901, Chapter 4. In addition, the waterproofing system of all Seismic Category I foundations subjected to aggressive environments will be evaluated for use in aggressive environments. Also, the concrete of Seismic Category I foundations subjected to aggressive environments will meet the durability requirements of ACI 34901, Chapter 4 or ASME, Section III, Division 2, Article CC2231.7, as applicable. 3.8.5.6.1 3.812 A COL applicant that references the U.S. EPR design certification will describe the program to examine inaccessible portions of belowgrade concrete structures for degradation and monitoring of groundwater chemistry. 3.8.5.7 3.813 A COL applicant that references the U.S. EPR design certification will identify if any sitespecific settlement monitoring requirements are required for Seismic Category I foundations based on sitespecific soil conditions. 3.8.5.7 3.814 A COL applicant that references the U.S. EPR design certification will describe the design and analysis procedures used for buried conduit and duct banks, and buried pipe and pipe ducts. 3.8.4.4.5 3.815 A COL applicant that references the U.S. EPR design certification will use results from site specific investigations to determine the routing of buried pipe and pipe ducts. 3.8.4.4.5 3.816 A COL applicant that references the U.S. EPR design certification will perform geotechnical engineering analyses to determine if the surface load will cause lateral and/or vertical displacement of bearing soil for the buried pipe and pipe ducts and consider the effect of wide or extra heavy loads. 3.8.4.4.5 3.91 A COL applicant that references the U.S. EPR design certification will submit the results from the vibration assessment program for the U.S. EPR RPV internals, and piping systems specified in U.S. EPR FSAR Tier 2, Section 3.9.2.1, in accordance with RG 1.20. 3.9.2.4 3.92 A COL applicant that references the U.S. EPR design certification will prepare the design specifications and design reports for ASME Class 1, 2, and 3 components, piping, supports and core support structures that comply with and are certified to the requirements of Section III of the ASME Code. The COL applicant will address the results and conclusions from the reactor internals material reliability programs applicable to the U.S. EPR reactor internals with regard to known aging degradation mechanisms such as irradiationassisted stress corrosion cracking and void swelling. 3.9.3 3.93 A COL applicant that references the U.S. EPR design certification will examine the feedwater line welds after hot functional testing prior to fuel loading and at the first refueling outage, in accordance with NRC Bulletin 7913. A COL applicant that references the U.S. EPR design certification will report the results of inspections to the NRC, in accordance with NRC Bulletin 7913. 3.9.3.1.1 3.94 As noted in ANP10264NPA, A COL applicant that references the U.S. EPR design certification will confirm that thermal deflections do not create adverse conditions during hot functional testing. 3.9.3.1.1 CCNPP Unit 3 1-38 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 Interfaces with Standard Designs and Early Site Permits Table 1.8-2— FSAR Sections that Address COL Items (Page 8 of 20) Item No. Description Section 3.95 As noted in ANP10264NPA, should a COL applicant that references the U.S. EPR design certification find it necessary to route Class 1, 2, and 3 piping not included in the U.S. EPR design certification so that it is exposed to wind and tornadoes, the design must withstand the plant designbasis loads for this event. 3.9.3.1.1 3.96 A COL applicant that references the US EPR design certification will identify any additional sitespecific valves in Table 3.9.62 to be included within the scope of the IST program. 3.9.6.3 3.97 A COL applicant that references the U.S. EPR design certification will submit the preservice testing (PST) program and IST program for pumps, valves, and snubbers as required by 10 CFR 50.55a. 3.9.6 3.98 A COL applicant that references the US EPR design certification will identify any additional sitespecific pumps in Table 3.9.61 to be included within the scope of the IST program. 3.9.6.2 3.99 COL applicant that references the U.S. EPR design certification will either use a piping analysis program based on the computer codes described in Section 3.9.1 and Appendix 3C or will implement a U.S. EPR benchmark program using models specifically selected for the U.S. EPR. 3.9.1.2 3.910 Pipe stress and support analysis will be performed by a COL applicant that references the U.S. EPR design certification. 3.9.1.2 3.911 A COL applicant that references the U.S. EPR design certification will provide a summary of the maximum total stress, deformation (where applicable), and cumulative usage factor values for each of the component operating conditions for ASME Code Class 1 components. For those values that differ from the allowable limits by less than 10 percent, the COL applicant will provide the contribution of each of the loading categories (e.g., seismic, pipe rupture, dead weight, pressure, and thermal) to the total stress for each maximum stress value identified in this range. The COL applicant will also provide the maximum total stress and deformation values for each operating condition for Class 2 & 3 components required for safe shutdown of the reactor, or mitigation of consequences of a postulated piping failure without offsite power. Identification of those values that differ from the allowable limits by less than 10 percent will also be provided. 3.9.3.1 3.912 A COL applicant that references the U.S.EPR design certification will provide a table identifying the safetyrelated systems and components that use snubbers in their support systems, including the number of snubbers, type (hydraulic or mechanical), applicable standard, and function (shock, vibration, or dualpurpose snubber). For snubbers identified as either a dualpurpose or vibration arrester type, the COL applicant shall indicate whether the snubber or component was evaluated for fatigue strength. 3.9.6.4 3.913 A COL applicant that references the U.S. EPR design certification will identify the implementation milestones and applicable ASME OM Code for the preservice and inservice examination and testing programs. These programs will be consistent with the requirements in the latest edition and addenda of the OM Code incorporated by reference in 10 CFR 50.55a on the date 12 months before the date for initial fuel load. 3.9.6 3.914 A COL applicant that references the U.S. EPR design certification will provide a summary of reactor core support structure maximum total stress, deformation, and cumulative usage factor values for each component and each operating condition in conformance with ASME Section III Subsection NG. 3.9.5.2 3.101 A COL applicant that references the U.S. EPR design certification will create and maintain the SQDP file during the equipment selection and procurement phase. 3.10.4 3.102 A COL applicant that references the U.S. EPR design certification will identify any additional site specific components that need to be added to the equipment list in Table 3.101. 3.10.1.1 3.103 If the seismic and dynamic qualification testing is incomplete at the time of the COL application, A COL applicant that references the U.S. EPR design certification will submit an implementation program, including milestones and completion dates, for NRC review and approval prior to installation of the applicable equipment. 3.10.4 3.111 A COL applicant that references the U.S. EPR design certification will maintain the equipment qualification test results and qualification status file during the equipment selection, procurement phase and throughout the installed life in the plant. CCNPP Unit 3 1-39 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED 3.11 Rev. 7 FSAR: Chapter 1.0 Interfaces with Standard Designs and Early Site Permits Table 1.8-2— FSAR Sections that Address COL Items (Page 9 of 20) Item No. Description Section 3.112 A COL applicant that references the U.S. EPR design certification will identify additional site specific components that need to be added to the environmental qualification list in Table 3.111. 3.113 If the equipment qualification testing is incomplete at the time of the COL application, a COL applicant that references the U.S. EPR design certification will submit an implementation program, including milestones and completion dates, for NRC review and approval prior to installation of the applicable equipment. 3.11.3 3.121 A COL applicant that references the U.S. EPR design certification will perform a review of the impact of contributing mass of supports on the piping analysis following the final support design to confirm that the mass of the support is no more than ten percent of the mass of the adjacent pipe span. 3.12.4.2 3.122 As indicated in Section 5.3 of topical report ANP10264NPA, pipe and support stress analysis will be performed by the COL applicant that references the U.S. EPR design certification. If the COL applicant that references the U.S. EPR design certification chooses to use a piping analysis program other than those listed in Section 5.1 of the topical report, the COL applicant will implement a benchmark program using models specifically selected for the U.S. EPR. 3.12.4.3 3.123 A COL applicant that references the U.S. EPR design certification will monitor the RHR/SIS/ EBS injection piping from the RCS to the first isolation valve (all four trains), and RHR/SIS suction piping from the RCS to the first isolation valve (trains 1 and 4) during the first cycle of the first U.S. EPR initial plant operation to verify that operating conditions have been considered in the design unless data from a similar plant’s operation demonstrates that thermal oscillation is not a concern for piping connected to the RCS. 3.12.5.9 3.124 A COL applicant that references the U.S. EPR design certification will monitor pressurizer surge line temperatures during the first fuel cycle of initial plant operation to verify that the design transients for the surge line are representative of actual plant operations. 3.12.5.10.1 3.125 A COL applicant that references the U.S. EPR design certification will monitor the normal spray line temperatures during the first cycle of the first U.S. EPR initial plant operation to verify that the design transients for the normal spray are representative of actual plan operations unless data from a similar plant’s operation determines that monitoring is not warranted. 3.12.5.10.3 3.126 A COL applicant that references the U.S. EOR design certification will monitor the temperature of the main feedwater lines during the first cycle of the first U.S. EPR initial plant operation to verify that the design transients for the main feedwater lines are representative of actual plant operations unless data from a similar plant’s operation determines that monitoring is not warranted. 3.12.5.10.4 3.131 A COL applicant referencing the U.S. EPR design certification will submit the inservice inspection program for ASME Code Class 1, Class 2, and Class 3 threaded fasteners, to the NRC prior to performing the first inspection. The program will identify the applicable edition and addenda of ASME Section XI and ensure compliance with the requirements of 10 CFR 50.55a(b)(2)(xxvii). 3.13.2 3E1 A COL applicant that references the U.S. EPR design certification will address critical sections relevant to sitespecific Seismic Category I structures. 3E 5.21 Deleted 5.22 A COL applicant that references the U.S. EPR design certification will identify additional ASME code cases to be used. 5.23 A COL applicant that references the U.S. EPR design certification will identify the implementation milestones for the sitespecific ASME Section XI preservice and inservice inspection program for the reactor coolant pressure boundary, consistent with the requirements of 10 CFR 50.55a (g). The program will identify the applicable edition and addenda of the ASME Code Section XI, and will identify additional relief requests and alternatives to Code requirements. 5.2.4 5.24 A COL applicant that references the U.S. EPR design certification will develop procedures in accordance with RG 1.45, Revision 1. 5.2.5 5.31 A COL applicant that references the U.S. EPR design certification will identify the implementation milestones for the material surveillance program. CCNPP Unit 3 1-40 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED 3.11.1.1.3 5.2.1.2 5.3.1.6 Rev. 7 FSAR: Chapter 1.0 Interfaces with Standard Designs and Early Site Permits Table 1.8-2— FSAR Sections that Address COL Items (Page 10 of 20) Item No. Description Section 5.32 A COL applicant that references the U.S. EPR design certification will provide a plantspecific pressure and temperature limits report (PTLR), consistent with an approved methodology. 5.3.2.1 5.33 A COL applicant that references the U.S. EPR design certification will provide plantspecific RTPTS values in accordance with 10 CFR 50.61 for vessel beltline materials. 5.3.2.3 5.34 A COL Applicant that references the U.S. EPR design certification will provide plant specific surveillance data to benchmark BAW2241PA and demonstrate applicability to the specific plant. 5.3.1.6 5.41 A COL applicant that references the U.S. EPR design certification will identify the edition and addenda of ASME Section XI applicable to the site specific Steam Generator inspection program. 5.4.2.5.2.2 6.11 A COL applicant that references the U.S. EPR design certification will review the fabrication and welding procedures and other QA methods of ESF component vendors to verify conformance with RGs 1.44 and 1.31. 6.1.1.1 6.12 If components cannot be procured with DBAqualified coatings applied by the component manufacturer, A COL applicant that references the U.S. EPR design certification must do one of the following: procure the component as uncoated and apply a DBAqualified coating system in accordance with 10 CFR 50 Appendix B, Criterion IX; confirm that the DBAunqualified coating is removed and the component is recoated with DBAqualified coatings in accordance with 10 CFR 50 Appendix B, Criterion IX; or add the quantity of DBAunqualified coatings to a list that documents those DBAunqualified coatings already existing within containment. 6.1.2.3.2 6.21 A COL applicant that references the U.S. EPR design certification will identify the implementation milestones for the CLRT program described under 10 CFR 50, Appendix J. 6.31 A COL applicant that references the U.S. EPR design certification will describe the containment cleanliness program which limits debris within containment. 6.41 A COL applicant that references the U.S. EPR design certification will identify the type(s) of Seismic Category I Class IE toxic gas sensors (i.e., the toxic chemical(s) of concern) necessary for control room operator protection. 6.4.6 6.42 A COL applicant that references the U.S. EPR design certification will provide written emergency planning and procedures in the event of a radiological or a hazardous chemical release within or near the plant, and will provide training of control room personnel. 6.4.3 6.43 A COL applicant that references the U.S. EPR design certification will evaluate the results of the toxic chemical accidents from Section 2.2.3 and address their impact on control room habitability in accordance with RG 1.78. 6.4.4 6.44 A COL applicant that references the U.S. EPR design certification will confirm that the radiation exposure of main control room occupants resulting from a design basis accident at a nearby unit on a multiunit site is bounded by the radiation exposure from the postulated design basis accidents analyzed for the U.S. EPR; or confirm that the limits of GDC19 are met. 6.4.4 6.61 A COL applicant that references the U.S. EPR design certification will identify the implementation milestones for the sitespecific ASME Section XI preservice and inservice inspection program for the Class 2 and Class 3 components, consistent with the requirements of 10 CFR 50.55a (g). The program will identify the applicable edition and addenda of the ASME Code Section XI, and will identify additional relief requests and alternatives to Code requirements. 6.6 7.11 A COL applicant that references the U.S. EPR design certification will update the initial inventory list of accident monitoring variables including variable types in Table 7.51 Initial Inventory of PostAccident Monitoring Variables, with a final list upon completion of the emergency procedure guidelines or the emergency operating and abnormal operating procedures prior to fuel loading. 8.11 A COL applicant that references the U.S. EPR design certification will provide sitespecific information describing the interface between the offsite transmission system, and the nuclear unit, including switchyard interconnections. 8.1.1 8.12 A COL applicant that references the U.S. EPR design certification will identify sitespecific loading differences that raise EDG or Class 1E battery loading, and demonstrate the electrical distribution system is adequately sized for the additional load. 8.1.3 CCNPP Unit 3 1-41 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED 6.2.6 6.3.2.2.2 7.5.2.2.1 Rev. 7 FSAR: Chapter 1.0 Interfaces with Standard Designs and Early Site Permits Table 1.8-2— FSAR Sections that Address COL Items (Page 11 of 20) Item No. Description Section 8.21 A COL applicant that references the U.S. EPR design certification will provide site specific information regarding the offsite transmission system and their connections to the station switchyard. 8.2.1.1 8.22 A COL applicant that references the U.S. EPR design certification will provide sitespecific information for the switchyard layout design. 8.2.1.2 8.23 A COL applicant that references the U.S. EPR design certification will provide sitespecific information that identifies actions necessary to restore offsite power and use available nearby power sources when offsite power is unavailable. 8.2.2.7 8.24 A COL applicant that references the U.S. EPR design certification will provide a sitespecific grid stability analysis. 8.2.2.4 8.25 A COL applicant that references the U.S. EPR design certification will provide sitespecific information for the protective devices that control the switchyard breakers and other switchyard relay devices. 8.2.1.2 8.26 A COL applicant that references the U.S. EPR design certification will provide sitespecific information for the station switchyard equipment inspection and testing plan. 8.2.2.5 8.27 A COL applicant that references the U.S. EPR design certification will provide site specific information regarding the communication agreements and protocols between the station and the transmission system operator, independent system operator, or reliability coordinator/authority. Additionally, the applicant will provide a description of the analysis tool used by the transmission system operator to determine, in real time, the impact that the loss or unavailability of various transmission system elements will have on the condition of the transmission system to provide posttrip voltages at the switchyard. The information provided will be consistent with information requested in NRC Generic Letter 200602. 8.2.1.1 8.28 A COL applicant that references the U.S. EPR design certification will provide sitespecific information regarding indication and control of switchyard components. 8.2.1.2 8.31 A COL applicant that references the U.S. EPR design certification will monitor and maintain EDG reliability during plant operations to verify the selected reliability level target is being achieved as intended by RG 1.155. 8.3.1.1.5 8.32 A COL applicant that references the U.S. EPR design certification will describe inspection, testing and monitoring programs to detect the degradation of inaccessible or underground power cables that support EDGs, offsite power, ESW and other systems that are within the scope of 10 CFR 50.65. 8.3.1.1.8 8.41 A COL applicant that references the U.S. EPR design certification will provide sitespecific information that identifies any additional local power sources and transmission paths that could be made available to resupply the power plant following a LOOP. 8.42 A COL applicant that references the U.S. EPR design certification will address the RG 1.155 guidance related to procedures and training to cope with SBO. 8.4.2.6.4 9.11 A COL applicant that references the U.S. EPR design certification will provide sitespecific information on the heavy load handling program, including a commitment to procedures for heavy load lifts in the vicinity of irradiated fuel or safe shutdown equipment, and crane operator training and qualification. 9.1.5.2.5 9.21 A COL applicant that references the U.S. EPR design certification will provide site specific information for the UHS support systems such as makeup water, blowdown, and chemical treatment (to control biofouling). 9.22 A COL applicant that references the U.S. EPR design certification will provide sitespecific details related to the sources and treatment of makeup to the potable and sanitary water system along with a simplified piping and instrument diagram. 9.2.4.2.1 9.23 The raw water supply system (RWSS) and the design requirements of the RWSS are site specific and will be addressed by the COL applicant. 9.2.9 9.24 A COL applicant that references the U.S. EPR design certification will provide a description of materials that will be used for the essential service water system (ESWS) at their site location, including the basis for determining that the materials being used are appropriate for the site location and for fluid properties that apply 9.2.1.3.5 CCNPP Unit 3 1-42 © 2007-2010 UniStar Nuclear Services, LLC. 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COPYRIGHT PROTECTED 8.4.1.3 9.2.5.2 Rev. 7 FSAR: Chapter 1.0 Interfaces with Standard Designs and Early Site Permits Table 1.8-2— FSAR Sections that Address COL Items (Page 12 of 20) Item No. Description Section 9.25 A COL applicant that references the U.S. EPR design certification will provide a description of materials that will be used for the UHS at their site location, including the basis for determining that the materials being used are appropriate for the site location and for the fluid properties that apply. 9.2.5.2 9.41 A COL applicant that references the U.S. EPR design certification will provide sitespecific design information for the turbine building ventilation system (TBVS). 9.4.4 9.42 A COL applicant that references the U.S. EPR design certification will provide sitespecific design information for the switchgear building ventilation system, turbine island (SWBVS). 9.4.4 9.51 A COL applicant referencing the U.S. EPR certified design will identify additional site specific communication locations necessary to support effective communication between plant personnel in all vital areas of the plant during normal operation, as well as during accident conditions. 9.52 A COL applicant that references the U.S. EPR design certification will submit site specific information to address the Regulatory Guide 1.189, Regulatory Position C.1.7.1, Design and Procurement Document Control. Table 9.5-1, C.1.7.1 9.53 A COL applicant that references the U.S. EPR design certification will submit site specific information to address the Regulatory Guide 1.189, Regulatory Position C.1.7.2, Instructions, Procedures and Drawings. Table 9.5-1, C.1.7.2 9.54 A COL applicant that references the U.S. EPR design certification will submit site specific information to address the Regulatory Guide 1.189, Regulatory Position C.1.7.3, Control of Purchased Material, Equipment, and Services. Table 9.5-1, C.1.7.3 9.55 A COL applicant that references the U.S. EPR design certification will submit site specific information to address the Regulatory Guide 1.189, Regulatory Position C.1.8, Fire Protection Program Changes/Code Deviations. Table 9.5-1, C.1.8 9.56 A COL applicant that references the U.S. EPR design certification will submit site specific information to address the Regulatory Guide 1.189, Regulatory Position C.1.8.1, Change Evaluations. Table 9.5-1, C.1.8.1 9.57 A COL applicant that references the U.S. EPR design certification will submit site specific information to address the Regulatory Guide 1.189, Regulatory Position C.1.8.5, 10 CFR 50.72 Notification and 10 CFR 50.73 Reporting. Table 9.5-1, C.1.8.5 9.58 A COL applicant that references the U.S. EPR design certification will submit site specific information to address the Regulatory Guide 1.189, Regulatory Position C.1.8.7, Fire Modeling. Table 9.5-1, C.1.8.7 9.59 A COL applicant that references the U.S. EPR design certification will submit site specific information to address the Regulatory Guide 1.189, Regulatory Position C.5.5, PostFire SafeShutdown Procedures. Table 9.5-1, C.5.5 9.510 A COL applicant that references the U.S. EPR design certification will submit site specific information to address the Regulatory Guide 1.189, Regulatory Position C.5.5.1, SafeShutdown Procedures. Table 9.5-1, C.5.5.1 9.511 A COL applicant that references the U.S. EPR design certification will submit site specific information to address the Regulatory Guide 1.189, Regulatory Position C.5.5.2, Alternative/ Dedicated Shutdown Procedures. Table 9.5-1, C.5.5.2 9.512 A COL applicant that references the U.S. EPR design certification will submit site specific information to address the Regulatory Guide 1.189, Regulatory Position C.5.5.3, Repair Procedures. Table 9.5-1, C.5.5.3 9.513 A COL applicant that references the U.S. EPR design certification will submit site specific information to address the Regulatory Guide 1.189, Regulatory Position C.6.2.4, Independent Spent Fuel Storage Areas. Table 9.5-1, C.6.2.4 9.514 A COL applicant that references the U.S. EPR design certification will submit site specific information to address the Regulatory Guide 1.189, Regulatory Position C.6.2.6, Cooling Towers. 9.5.1.2.1 9.515 A COL applicant that references the U.S. EPR design certification will submit site specific information to address Regulatory Guide 1.189, Regulatory Position C.7.6, Nearby Facilities. Table 9.5-1, C.7.6 CCNPP Unit 3 1-43 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED 9.5.2.3 Rev. 7 FSAR: Chapter 1.0 Interfaces with Standard Designs and Early Site Permits Table 1.8-2— FSAR Sections that Address COL Items (Page 13 of 20) Item No. Description Section 9.516 A COL applicant that references the U.S. EPR design certification will perform an asbuilt, postfire Safe Shutdown Analysis, which includes final plant cable routing, fire barrier ratings, purchased equipment, equipment arrangement and includes a review against the assumptions and requirements contained in the Fire Protection Analysis. The postfire Safe Shutdown Analysis will demonstrate that safe shutdown performance objectives are met prior to fuel loading and will include a postfire safe shutdown circuit analysis based on the methodology described in NEI 0001, ”Guidance for PostFire SafeShutdown Circuit Analysis.” 9.5.1.2.1 9.517 A COL applicant that references the U.S. EPR design certification will evaluate the differences between the asdesigned and asbuilt plant configuration to confirm the Fire Protection Analysis remains bounding. This evaluation will be performed prior to fuel loading and will consider the final plant cable routing, fire barrier ratings, combustible loading, ignition sources, purchased equipment, equipment arrangement and includes a review against the assumptions and requirements contained in the Fire Protection Analysis. The applicant will describe how this asbuilt evaluation will be performed and documented, and how the NRC will be made aware of deviations from the FSAR, if any. 9.5.1.3 9.518 A COL applicant that references the U.S. EPR design certification will perform a supplemental Fire Protection Analysis for sitespecific areas of the plant not analyzed bv the FSAR. 9.5.1.3 9.519 A COL applicant that references the U.S. EPR design certification will provide a description and simplified Fire Protection System piping and instrumentation diagrams for sitespecific systems. 9.5.1.2.1 9.520 A COL applicant that references the U.S. EPR design certification will describe the program used to monitor and maintain an acceptable level of quality in the fire protection system freshwater storage tanks. 9.5.1.2.1 9.521 A COL applicant that references the U.S. EPR design certification will provide a description of the offsite communication system that interfaces with the onsite communication system, including type of connectivity, radio frequency, normal and backup power supplies and plant security system interface. 9.5.2.1.1 9.5.4.4 9.522 A COL applicant that references the U.S. EPR design certification will describe the sitespecific sources of acceptable fuel oil available for refilling the EDG fuel oil storage tanks within seven days, including the means of transporting and refilling the fuel storage tanks, following a design basis event to enable each diesel generator system to supply uninterrupted emergency power. 10.01 Deleted 10.21 Deleted 10.22 A COL applicant that references the U.S. EPR design certification will provide applicable material properties of the turbine rotor, including the method of calculating the fracture toughness properties, after the site specific turbine has been procured. 10.2.3.1 10.23 A COL applicant that references the U.S. EPR design certification will provide applicable turbine disk rotor specimen test data, load displacement data from the compact tension specimens and the fracture toughness properties after the sitespecific turbine has been procured. 10.2.3.2 10.24 A COL applicant that references the U.S. EPR design certification will provide schematics and logic diagrams for the turbine control system. 10.2.2.5 10.25 A COL applicant that references the U.S. EPR design certification will provide the sitespecific turbine rotor inservice inspection program and inspection interval consistent with the manufacturer’s turbine missile analysis. 10.2.3.6 10.31 A COL applicant that references the U.S. EPR design certification will identify the authority responsible for implementation and management of the secondary side water chemistry program. 10.3.5 10.32 A COL applicant that references the U.S. EPR design certification will develop and implement a FAC condition monitoring program that is consistent with Generic Letter 8908 and NSAC202LR3 for the carbon steel portions of the steam and power conversion systems that contain water or wet steam prior to initial fuel loading. 10.3.6.3 10.41 A COL applicant that references the U.S. EPR design certification will describe the sitespecific main condenser materials. 10.4.1.2 CCNPP Unit 3 1-44 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 Interfaces with Standard Designs and Early Site Permits Table 1.8-2— FSAR Sections that Address COL Items (Page 14 of 20) Item No. Description Section 10.42 A COL applicant that references the U.S. EPR design certification will describe the sitespecific design pressure and test pressure for the main condenser. 10.43 A COL applicant that references the U.S. EPR design certification will provide the description of the sitespecific portions of the CWS. 10.4.5.2.1 10.44 A COL applicant that references the U.S. EPR design certification will provide the specific chemicals used within the chemical treatment system as determined by the sitespecific water conditions. 10.4.5.2.2 10.45 A COL applicant that references the U.S. EPR design certification will provide the sitespecific CWS piping design pressure. 10.4.5.2.2 10.46 If a vacuum priming system is required, a COL applicant that references the U.S. EPR design certification will provide the sitespecific information. 10.4.5.2.2 10.47 A COL applicant that references the U.S. EPR design certification will provide information to address the potential for flooding of safetyrelated equipment due to failures of the sitespecific CWS. 10.4.5.3 11.21 A COL applicant that references the U.S. EPR design certification will perform a sitespecific liquid waste management system costbenefit analysis. 11.2.4 11.22 A COL applicant that references the U.S. EPR design certification will provide sitespecific information on the release pathway, including a detailed description of the discharge path and plant sources of dilution, the discharge flow rate, and dilution factors at or beyond the point of discharge. 11.23 A COL applicant that references the U.S. EPR design certification will confirm that the sitespecific parameters are bounded by those provided in Table 11.25 and the dose pathways provided in Section 11.2.3.4.1. For sitespecific parameters that are not bounded by the values provided in Table 11.25 and dose pathways other than those provided in Section 11.2.3.4.1, a COL applicant that references the U.S. EPR design certification will perform a sitespecific liquid pathway dose analysis following the guidance provided in RG 1.109 and RG 1.113, and compare the doses to the numerical design objectives of 10 CFR Part 50, Appendix I and demonstrate compliance with requirements of 10 CFR Part 20.1302 and 40 CFR Part 190. 11.2.3.4.2 11.24 A COL applicant that references the U.S. EPR design certification will confirm that the sitespecific annual average liquid effluent concentrations are bounded by those specified in Table 11.27. For sitespecific annual average liquid effluent concentrations that exceed the values provided in Table 11.27, a COL applicant that references the U.S. EPR design certification will demonstrate that the annual average liquid effluent concentrations for expected and design basis conditions meet the limits of 10 CFR Part 20, Appendix B, Table 2 in unrestricted areas. 11.2.3.5 11.25 A COL applicant that references the U.S. EPR design certification will confirm that the sitespecific data (such as distance from release location to unrestricted area, contaminant migration time, and dispersion and dilution in surface or ground water) are bounded by those specified in Section 11.2.3.7. For sitespecific parameters that exceed the values provided in Section 11.2.3.7, a COL applicant that references the U.S. EPR design certification will provide a sitespecific analysis to demonstrate that the resulting water concentrations in the unrestricted area would meet the concentration limits of 10 CFR Part 20, Appendix B, Table 2 using the guidance provided in SRP Sections 2.4.12, 2.4.13, 11.2 and BTP 116. 11.2.3.7 11.26 A COL applicant that references the U.S. EPR design certification and that chooses to install and operate mobile skidmounted processing systems connected to permanently installed LWMS processing equipment will include plant and sitespecific information describing how design features and implementation of operating procedures for the LWMS will address the requirements of 10 CFR Part 20.1406(b) and guidance of SRP Section 11.2, RG 4.21 and 1.143, IE Bulletin 8010, and NEI 0808. 11.2.1.2.4 11.31 A COL applicant that references the U.S. EPR design certification will perform a sitespecific gaseous waste management system costbenefit analysis. 11.32 A COL applicant that references the U.S. EPR design certification will provide a discussion of the onsite vent stack design parameters and sitespecific release point characteristics. CCNPP Unit 3 1-45 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED 10.4.1.2 11.2.3.3 11.3.4 11.3.3.3 Rev. 7 FSAR: Chapter 1.0 Interfaces with Standard Designs and Early Site Permits Table 1.8-2— FSAR Sections that Address COL Items (Page 15 of 20) Item No. Description Section 11.33 A COL applicant that references the U.S. EPR design certification will confirm that the sitespecific parameters are bounded by those provided in Table 11.34 and the dose pathways provided in Section 11.3.3.4. For sitespecific parameters that are not bounded by the values provided in Table 11.34 and dose pathways other than those provided in Section 11.3.3.4, a COL applicant that references the U.S. EPR design certification will perform a sitespecific gaseous pathway dose analysis following the guidance provided in RG 1.109 and RG 1.111, and compare the doses to the numerical design objectives of 10 CFR Part 50, Appendix I and demonstrate compliance with requirements of 10 CFR Part 20.1302 and 40 CFR Part 190. 11.3.3.4 11.34 A COL applicant that references the U.S. EPR design certification will confirm that the sitespecific annual average gaseous effluent concentrations are bounded by those specified in Table 11.36. For sitespecific annual average gaseous effluent concentrations that exceed the values provided in Table 11.36, a COL applicant that references the U.S. EPR design certification will demonstrate that the annual average gaseous effluent concentrations for expected and design basis conditions meet the limits of 10 CFR Part 20, Appendix B, Table 2 in unrestricted areas. 11.3.3.5 11.35 A COL applicant that references the U.S. EPR design certification will confirm that the sitespecific accident atmospheric dispersion data is bounded by the values provided in Table 2.11. For sitespecific accident atmospheric dispersion data that exceed the values provided in Table 2.11, a COL applicant that references the U.S. EPR design certification will provide a sitespecific analysis demonstrating that the resulting dose at the exclusion area boundary associated with a radioactive release due to gaseous waste system leak or failure does not exceed 0.1 rem in accordance with SRP Section 11.3, BTP 115. 11.3.3.6 11.36 A COL applicant that references the U.S. EPR design certification and that chooses to install and operate mobile skidmounted processing systems connected to permanently installed GWMS processing equipment will include plant and sitespecific information describing how design features and implementation of operating procedures for the GWMS will address the requirements of 10 CFR Part 20.1406(b) and guidance of SRP Section 11.3, RG 4.21, RG 1.143, IE Bulletin 8010, and NEI 0808. 11.3.1.2.4 11.41 A COL Applicant that references the U.S. EPR design certification will fully describe, at the functional level, elements of the Process Control Program (PCP). This program description will identify the administrative and operational controls for waste processing process parameters and surveillance requirements which demonstrate that the final waste products meet the requirements of applicable federal, state, and disposal site waste form requirements for burial at a 10 CFR 61 licensed low level disposal site, toxic or hazardous waste requirements per 10 CFR 20.2007, and will be in accordance with the guidance provided in RG 1.21, NUREG0800 Branch Technical Position 113, ANSI/ANS55.11992, and Generic Letters 8009, 8138, and 8139. NEI 0710A PCP Template is an alternate means of demonstrating compliance with GL 8901 and SECY 050197 until a plant specific PCP is developed under license conditions. 11.4.3 11.42 A COL applicant that references the U.S. EPR design certification and that chooses to install and operate mobile skidmounted processing systems connected to permanently installed solid waste management system (SWMS) processing equipment will include plant and sitespecific information describing how design features and implementation of operating procedures for the SWMS will address the requirements of 10 CFR Part 20.1406(b) and guidance of SRP Section 11.4, Regulatory Guides 4.21 and 1.143, IE Bulletin 8010, industry standards, and NEI 0808. 11.4.1 11.43 A COL applicant that references the U.S. EPR design certification will address plantspecific commitments to address the longterm storage of LLRW beyond the provisions described in the U.S. EPR design certification when such storage capacity is exhausted and describe how additional onsite LLRW storage or alternate LLRW storage will be integrated in plant operations. To address the need for additional storage, the commitment will address the requirements of 10 CFR Part 20, Appendix B (Table 2, Column 1 and 2); dose limits of 10 CFR 20.1301, 20.1302, and 20.1301(e) in unrestricted areas; Part 20.1406(b) in minimizing the contamination of plant facilities and environs; and design objectives of Sections II.A, II.B, II.C, and II.D of Appendix I to 10 CFR Part 50. The design and operations of additional onsite storage capacity will be integrated in the plantspecific process control program and consider the guidance of SRP Section 11.4 and Appendix 11.4A, Regulatory Guides 1.206, 4.21 and 1.143, IE Bulletin 8010, industry standards, and NEI 0808 11.4.1 CCNPP Unit 3 1-46 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 Interfaces with Standard Designs and Early Site Permits Table 1.8-2— FSAR Sections that Address COL Items (Page 16 of 20) Item No. Description Section 11.51 A COL applicant that references the U.S. EPR design certification will fully describe, at the functional level, elements of the process and effluent monitoring and sampling programs required by 10 CFR Part 50 Appendix I, and 10 CFR 52.79 (a)(16). This program description, Offsite Dose Calculation Manual (ODCM), will specify how a licensee controls, monitors, and performs radiological evaluations of releases. The program will also document and report radiological effluents discharged to the environment. NEI 0709A is an alternate means of demonstrating compliance with GL 8901 and SECY 050197 until a plant and sitespecific ODCM is developed under a license condition. NEI 079A is an alternate means of demonstrating compliance with GL 8901 and SECY 050197 until a plant and sitespecific ODCM is developed under a license condition. 11.5.2 11.52 A COL applicant that references the U.S. EPR design certification and that chooses to install and operate skidmounted radiation monitoring and sampling systems connected to permanently installed radioactive process and waste management systems will include plantspecific information describing how design features and implementation of operating procedures for the PERMSS will address the requirements of 10 CFR Part 20.1406(b) and guidance of SRP Section 11.5, Regulatory Guides 4.21 and 1.143, IE Bulletin 8010, ANSI/HPS13.11999 and ANSI N42.182004, and NEI 0808. 11.5.1 11.53 A COL applicant that references the U.S. EPR design certification is responsible for deriving PERMSS subsystem’s lower limits of detection or detection sensitivities, and setpoints (alarms and process termination/diversion) for liquid and gaseous process radiation monitoring equipment not covered by the ODCM based on plant and sitespecific conditions and operating characteristics of each installed radiation monitoring subsystem. 11.5.2 11.54 A COL applicant that references the U.S. EPR design certification is responsible for developing a plantspecific process and effluent radiological sampling and analysis plan for systems not covered by the ODCM, including provisions describing sampling and analytical frequencies, and radiological analyses for the expected types of liquid and gaseous samples and waste media generated by the LWMS, GWMS, and SWMS. 11.5.2 12.11 A COL applicant that references the U.S. EPR design certification will fully describe, at a functional level, elements of the ALARA program for ensuring that occupational radiation exposures are ALARA. This program will comply with provisions of 10 CFR Part 20 and be consistent with the guidance in RGs 1.8, 8.2, 8.7, 8.8, 8.9, 8.10, 8.13, 8.15, 8.27, 8.28, 8.29, 8.34, 8.35, 8.36, and 8.38, and the applicable portions of NUREG1736. 12.1.3 12.21 A COL applicant that references the U.S. EPR design certification will provide sitespecific information for required radiation sources containing byproduct, source, and special nuclear material that may warrant shielding design considerations. This sitespecific information will include a listing of isotope, quantity, form, and use of all sources in this latter category that exceed 100 millicuries. 12.2.1.13 12.31 A COL applicant that references the U.S. EPR design certification will provide sitespecific information on the extent to which the guidance provided by RG 1.21, 1.97, 8.2, 8.8, and ANSI/ HPSN13.11999 is employed in sampling recording and reporting airborne releases of radioactivity. 12.3.4.5 12.32 A COL applicant that references the U.S. EPR design certification will provide sitespecific information on estimated annual doses to construction workers in a new unit construction area as a result of radiation from onsite radiation sources from the existing operating plant(s). This information will include bases, models, assumptions, and input parameters associated with these annual doses. 12.3.5.1 12.33 A COL applicant that references the U.S. EPR design certification will describe the use of portable instruments, and the associated training and procedures, to accurately determine the airborne iodine concentration within the facility where plant personnel may be present during an accident, in accordance with requirements of 10 CFR 50.34(f)(2)(xxvii) and the criteria in Item III.D.3.3 of NUREG0737. The procedures for locating suspected highactivity areas will be described. 12.3.4.5 CCNPP Unit 3 1-47 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 Interfaces with Standard Designs and Early Site Permits Table 1.8-2— FSAR Sections that Address COL Items (Page 17 of 20) Item No. Description Section 12.51 A COL applicant that references the U.S. EPR design certification will fully describe, at the functional level, elements of the Radiation Protection Program. The purpose of the Radiation Protection Program is to maintain occupational and public doses ALARA. The program description will identify how the program is developed, documented, and implemented through plant procedures that address quality requirements commensurate with the scope and extent of licensed activities. This program will comply with the provisions of 10 CFR Parts 19, 20, 50, 52, and 71 and be consistent with the guidance in Regulatory Guides 1.206, 1.8, 8.2, 8.4, 8.5, 8.6, 8.7, 8.8, 8.9, 8.10, 8.13, 8.15, 8.27, 8.28, 8.29, 8.34, 8.35, 8.36, 8.38, and the consolidated guidance in NUREG1736. 12.5 13.11 A COL applicant that references the U.S. EPR design certification will provide sitespecific information for management, technical support, and operating organizations. 13.1 13.21 A COL applicant that references the U.S. EPR design certification will provide sitespecific information for training programs for plant personnel. 13.2 13.31 A COL applicant that references the U.S. EPR design certification will provide a sitespecific emergency plan in accordance with 10 CFR 50.47 and 10 CFR 50 Appendix E. 13.3 13.41 A COL applicant that references the U.S. EPR design certification will provide sitespecific information for operational programs and schedule for implementation. 13.4 13.51 A COL applicant that references the U.S. EPR design certification will provide sitespecific information for administrative, operating, emergency, maintenance, and other operating procedures. 13.5 13.61 A COL applicant that references the U.S. EPR design certification will provide a sitespecific security assessment that adequately demonstrates how the performance requirements of 10 CFR 73.55(a) are met for the initial implementation of the security program. 13.6 13.62 A COL applicant that references the U.S. EPR design certification will provide a security plan to the NRC to fulfill the requirements of 10 CFR 52.79(a)(35). 13.6 13.63 A COL applicant that references the U.S. EPR design certification will provide a security program through the PSP and supporting documents such as the vital equipment list and the vital areas list that incorporates the security features listed in the U.S. EPR FSAR Tier 2, Section 13.6. 13.6 13.64 A COL applicant that references the U.S. EPR design certification will provide a cyber security plan consistent with 10 CFR 73.54. 13.6 13.71 A COL applicant that references the U.S. EPR design certification will submit a physical security plan to the NRC to fulfill the fitness for duty requirements of 10 CFR Part 26. 13.7 14.21 A COL applicant that references the U.S. EPR certified design will provide site specific information that describes the organizational units that manage, supervise, or execute any phase of the test program. 14.2.2 14.22 A COL applicant that references the U.S. EPR certified design will develop a test program that considers the following guidance components: 1) The applicant should allow at least nine months to conduct preoperational testing. 2) The applicant should allow at least three months to conduct startup testing, including fuel loading, lowpower tests, and powerascension tests. 3) Plant safety will not be dependent on the performance of untested SSCs during any phase of the startup test program. 4) Surveillance test requirements will be completed in accordance with plant Technical Specification requirements for SSC operability before changing plant modes. 5) Overlapping test program schedules (for multiunit sites) should not result in significant divisions of responsibilities or dilutions of the staff provided to implement the test program. 6) The sequential schedule for individual startup tests should establish, insofar as practicable, that test requirements should be completed prior to exceeding 25 percent power for SSC that are relied on to prevent, limit, or mitigate the consequences of postulated accidents. 7) Approved test procedures should be in a form suitable for review by regulatory inspectors at least 60 days prior to their intended use or at least 60 days prior to fuel loading for fuel loading and startup test procedures. 8) Identify and cross reference each test (or portion thereof) required to be completed before initial fuel loading and that is designed to satisfy the requirements for completing ITAAC. 14.2.11 14.23 A COL applicant that references the US EPR design certification will provide sitespecific information for review and approval of test procedures. 14.2.3 CCNPP Unit 3 1-48 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 Interfaces with Standard Designs and Early Site Permits Table 1.8-2— FSAR Sections that Address COL Items (Page 18 of 20) Item No. Description Section 14.24 A COL applicant that references the US EPR design certification will address the sitespecific administrative procedures for review and approval of test results. 14.2.5 14.25 A COL applicant that references the U.S. EPR design certification will provide sitespecific test abstract information for the circulating water supply system. 14.2.12 14.26 A COL applicant that references the U.S. EPR certified design will either perform the natural circulation test (Test #196) or provide justification for not performing the test. The need to perform the test will be based on evaluation of previous natural circulation test results and a comparison of reactor coolant system (RCS) hydraulic resistance coefficients applicable to normal flow conditions. 14.2.12 14.27 A COL applicant that references the U.S. EPR design certification will provide sitespecific test abstract information for the cooling tower. 14.2.12 14.28 A COL applicant that references the U.S. EPR design certification will provide sitespecific test abstract information for the raw water supply system. 14.2.12 14.29 A COL applicant that references the U.S. EPR design certification will provide sitespecific test abstract information for personnel radiation monitors. 14.2.12 14.210 A COL applicant that references the U.S. EPR design certification will plan, and subsequently conduct, the plant startup test program. 14.2.4 14.211 A COL applicant that references the U.S. EPR design certification will identify the specific operator training to be conducted as part of the lowpower testing program related to the resolution of TMI Action Plan Item I.G.1, as described in (1) NUREG0660 NRC Action Plans Developed as a Result of the TMI2 Accident, Revision 1, August 1980, (2) NUREG0694 TMIRelated Requirements for New Operating Licenses, June 1980, and (3) NUREG0737 Clarification of TMI Action Plan requirements. 14.2.9 14.212 A COL applicant that references the U.S. EPR design certification will provide sitespecific test abstract information for plant laboratory equipment. 14.2.12 14.213 A COL applicant that references the U.S. EPR design certification will provide sitespecific test abstract information for the turbine island ventilation systems. 14.3 14.31 A COL applicant that references the U.S. EPR design certification will provide ITAAC for emergency planning, physical security, and site specific portions of the facility that are not included in the Tier 1 ITAAC associated with the certified design (10 CFR 52.80(a)). 14.3 14.32 A COL applicant that references the U.S. EPR design certification will describe the selection methodology for sitespecific SSCs to be included in ITAAC, if the selection methodology is different from the methodology described within the FSAR, and will also provide the selection methodology associated with emergency planning and physical security hardware. 14.3 14.33 A COL applicant that references the U.S. EPR design certification will identify a plan for implementing DAC. The plan will identify 1) the evaluations that will be performed for DAC, 2) the schedule for performing these evaluations, and 3) the associated design processes and information that will be available to the NRC for audit. 14.3 15.01 A COL applicant that references the U.S. EPR design certification will provide for staff review, prior to the first cycle of operation, the analysis results demonstrating that the uncompensated DNBR and LPD satisfies the SAFDL with a 95/95 assurance in accordance with ANP10287P. 15.0 16.01 Reviewer’s Notes and brackets are used to identify information or characteristics that are plant specific or are based on preliminary design information. A COL applicant that references the U.S. EPR design certification will provide the necessary information in response to the Reviewer’s Notes and replace preliminary information provided in brackets of the Technical Specifications and Technical Specification Bases with plant specific values. 16.0 17.21 A COL applicant that references the U.S. EPR design certification will provide the Quality Assurance Programs associated with the construction and operations phases. 17.2 17.41 A COL applicant that references the U.S. EPR design certification will identify the sitespecific SSCs within the scope of the RAP. 17.4.2 CCNPP Unit 3 1-49 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 Interfaces with Standard Designs and Early Site Permits Table 1.8-2— FSAR Sections that Address COL Items (Page 19 of 20) Item No. Description Section 17.42 A COL applicant that references the U.S. EPR design certification will provide the information requested in Regulatory Guide 1.206, Section C.I.17.4.4. 17.4.4 17.61 A COL applicant that references the U.S. EPR design certification will describe the process for determining which plant structures, systems, and components (SSC) will be included in the scope of the Maintenance Rule Program in accordance with 10 CFR 50.65(b). The program description will identify that additional SSC functions may be added to or subtracted from the Maintenance Rule scope prior to fuel load, when additional information is developed (e.g., emergency operating procedures, or EOP), and after the license is issued. 17.6.1 17.62 A COL applicant that references the U.S. EPR design certification will provide the process for determining which SSC within the scope of the Maintenance Rule program will be tracked to demonstrate effective control of their performance or condition in accordance with 10 CFR 50.65(a)(2). 17.6.2 17.63 A COL applicant that references the U.S. EPR design certification will provide a program description for monitoring SSC in accordance with 10 CFR 50.65(a)(1). 17.6.2 17.64 A COL applicant that references the U.S. EPR design certification will identify and describe the program for periodic evaluation of the Maintenance Rule program in accordance with 10 CFR 50.65(a)(3). 17.6.3 17.65 A COL applicant that references the U.S. EPR design certification will describe the program for maintenance risk assessment and management in accordance with 10 CFR 50.65(a)(4). Since the removal of multiple SSC from service can lead to a loss of Maintenance Rule functions, the program description will address how removing SSC from service will be evaluated. For qualitative risk assessments, the program description will explain how the risk assessment and management program will preserve plantspecific key safety functions. 17.6.4 17.66 A COL applicant that references the U.S. EPR design certification will describe the program for selection, training, and qualification of personnel with MaintenanceRulerelated responsibilities consistent with the provisions of Section 13.2 as applicable. Training will be commensurate with maintenance rule responsibilities, including Maintenance Rule Program administration, the expert panel process, operations, engineering, maintenance, licensing, and plant management. 17.6.5 17.67 A COL applicant that references the U.S. EPR design certification will describe the relationship and interface between Maintenance Rule Program and the Reliability Assurance Program. 17.6.6 17.68 A COL applicant that references the U.S. EPR design certification will describe the plan or process for implementing the Maintenance Rule Program as described in the COL application, which includes establishing program elements through sequence and milestones and monitoring or tracking the performance and/or condition of SSC as they become operational. The Maintenance Rule Program will be implemented by the time that fuel load is authorized. 17.6.8 17.69 A COL applicant that references the U.S. EPR design certification will describe the program for Maintenance Rule implementation. 17.6 18.11 A COL applicant that references the U.S. EPR design certification will execute the NRC approved HFE program as described in this section. 18.1 18.12 A COL applicant that references the U.S. EPR design certification will be responsible for HFE design implementation for a new Emergency Operations Facility (EOF) and/or Operational Support Center (OSC) and changes resulting from the addition of the U.S. EPR to an existing EOF and/or OSC. 18.1.1.3 18.51 A COL applicant that references the U.S. EPR design will confirm that actual staffing levels and qualifications of plant personnel specified in Section 13.1 of the COL application remain bounded by regulatory requirements and results of the staffing and qualifications analysis. 18.5 18.81 A COL applicant that references the U.S. EPR design certification will describe how HFE principles and criteria are incorporated into the development program for site procedures. 18.8 18.91 A COL applicant that references the U.S. EPR design certification will describe how HFE principles and criteria are incorporated into the development of training program scope, structure, and methodology. 18.9 18.121 A COL applicant that references the U.S. EPR design certification will implement a human performance monitoring program similar to that which is described in this section. 18.12 CCNPP Unit 3 1-50 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 Interfaces with Standard Designs and Early Site Permits Table 1.8-2— FSAR Sections that Address COL Items (Page 20 of 20) Item No. Description Section 19.01 A COL applicant that references the U.S. EPR design certification will either confirm that the PRA in the design certification bounds the site specific design information and any design changes or departures, or update the PRA to reflect the sitespecific design information and any design changes or departures. 19.0 19.11 A COL applicant that references the U.S. EPR design certification will describe the uses of PRA in support of licensee programs and identify and describe riskinformed applications being implemented during the combined license application phase. 19.1.1.2 19.12 A COL applicant that references the U.S. EPR design certification will describe the uses of PRA in support of licensee programs and identify and describe riskinformed applications being implemented during the construction phase. 19.1.1.3 19.13 A COL applicant that references the U.S. EPR design certification will describe the uses of PRA in support of licensee programs and identify and describe any riskinformed applications being implemented during the operational phase. 19.1.1.4 19.14 A COL applicant that references the U.S. EPR design certification will conduct a peer review of the PRA relative to the ASME PRA Standard prior to use of the PRA to support riskinformed applications or before fuel load. 19.1.2.3 19.15 A COL applicant that references the U.S. EPR design certification will describe the applicant’s PRA maintenance and upgrade program. 19.16 A COL applicant that references the U.S. EPR design certification will confirm that the designspecific U.S. EPR PRAbased seismic margins assessment is bounding for their specific site. 19.17 A COL applicant that references the U.S. EPR design certification will perform the sitespecific screening analysis and the sitespecific risk analysis for external events applicable to their site, including a sitespecific PRAbased SMA for soil effects (including sliding and overturning, liquefaction, and slope failure). 19.1.5.4 19.18 A COL applicant that references the U.S. EPR design certification will describe the uses of PRA in support of sitespecific design programs and processes during the design phase. 19.1.1.1 19.19 A COL applicant that references the U.S. EPR design certification will review asdesigned and asbuilt information and conduct walkdowns as necessary to confirm that the assumptions used in the PRA (including PRA inputs to RAP and SAMDA) remain valid with respect to internal events, internal flood and fire events (routings and locations of pipe, cable and conduit), and HRA analyses (development of operating procedures, emergency operating procedures and severe accident management guidelines and training), external events including PRAbased seismic margins HCLPF fragilities, and LPSD procedures. 19.1.2.2 19.21 A COL applicant that references the U.S. EPR design certification will develop and implement severe accident management guidelines prior to fuel loading using the Operating Strategies for Severe Accidents (OSSA) methodology described in U.S. EPR FSAR Section 19.2.5. CCNPP Unit 3 1-51 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED 19.1.2.4.1 19.1.5.1.2.4 19.2.5 Rev. 7 FSAR: Chapter 1.0 1.9 Conformance with Regulatory Criteria CONFORMANCE WITH REGULATORY CRITERIA This section of the U.S. EPR FSAR is incorporated by reference with the following supplements. The U.S. EPR FSAR includes the following COL Item in Section 1.9: A COL applicant that references the U.S. EPR design certification will review and address the conformance with regulatory criteria in effect six months before the docket date of the COL application for the sitespecific portions and operational aspects of the facility design. This COL Item is addressed as follows: A guide to U.S. EPR conformance with regulatory criteria is presented in Section 1.9 of the U.S. EPR FSAR. Conformance with regulatory criteria was summarized in Sections 1.9.1 through 1.9.5 of the U.S. EPR FSAR, including four conformance demonstration tables. These four conformance demonstration tables include U.S. EPR FSAR Table 1.9–2, U.S. EPR Conformance with Regulatory Guides, U.S. EPR FSAR Table 1.9–3, U.S. EPR Conformance with TMI Requirements (10 CFR 50.34(f)) and Generic Issues (NUREG0933), U.S. EPR FSAR Table 1.9–4, U.S. EPR Conformance with Advanced and Evolutionary LightWater Reactor Design Issues (SECY93087), Table 1–2, U.S. EPR Conformance with Standard Review Plan (NUREG0800) from ANP10292, U.S. EPR Conformance with Standard Review Plan (NUREG0800) Technical Report (AREVA 2009). Codes used to indicate conformance determinations in the ”U.S. EPR Assessment” columns of the four conformance demonstration tables are listed in Table 1.91 of the U.S. EPR FSAR. The definition of the conformance code ”N/ACOL” is: Guidance addresses concerns not addressed with the context of a design certification application and must be addressed by a combined license (COL) applicant referencing the U.S. EPR design certification. Sitespecific conformance to relevant aspects of the associated NRC guidance, as stipulated within the specific context of the cited guidance statement, was assessed for the regulatory guidance assigned a code of ”N/ACOL” in the four conformance demonstration tables of the U.S. EPR FSAR. Regulatory guidance not applicable to {CCNPP Unit 3} or not within the scope of the FSAR is not identified as nonconforming. Therefore, exceptions to this nonapplicable regulatory guidance are not required. For example, Regulatory Guide 1.81, Shared Emergency and Shutdown Electric Systems for MultiUnit Nuclear Power Plants, is not applicable to {CCNPP Unit 3} since it does not share emergency or shutdown electric systems with {CCNPP Units 1 and 2}. The results of these assessments are presented in Sections 1.9.1, 1.9.2, 1.9.3, and 1.9.5. Conformance with regulatory criteria associated with operational experience (generic communications) is addressed in Section 1.9.4. 1.9.1 Conformance with Regulatory Guides Sitespecific assessment of conformance with the regulatory guidance identified with a code of ”N/ACOL” in Table 1.92 of the U.S. EPR FSAR was performed. Those Regulatory Guides for which the facility takes exception are identified in Table 1.9-1. The document and section that address the exceptions are also provided in Table 1.9-1. No exceptions are taken to other applicable Regulatory Guides included in U.S. EPR FSAR Table 1.92. CCNPP Unit 3 1-52 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 1.9.2 Conformance with Regulatory Criteria Conformance with the Standard Review Plan Sitespecific assessment of conformance with regulatory guidance identified with a code of ”N/ACOL” in Table 12 of ANP10292 (AREVA, 2009) was performed. No exceptions are taken to the applicable NUREG0800 acceptance criteria included in ANP10292, Table 12. 1.9.3 Generic Issues Assessment of the conformance with regulatory requirements and guidance identified with a code of ”N/ACOL” in Table 1.93 of the U.S. EPR FSAR was performed. {CCNPP Unit 3} conforms to the regulatory requirements and applicable regulatory guidance in effect six months prior to the submittal date of the COL application that were assigned an assessment code of ”N/ACOL” in Table 1.93 of the U.S. EPR FSAR. 1.9.4 Operational Experience (Generic Communications) Operational experience described in Bulletins and Generic Letters are incorporated by the NRC staff into updates of applicable sections of NUREG0800. The U.S. EPR design certification application was submitted May29, 2009 (AREVA, 2009) and addressed conformance with the most recent NUREG0800 updates relative to the U.S. EPR design certification application, March 2007 (for NUREG0800 Chapters 118) and June 2007 (for NUREG0800 Chapter 19). {In the time period from the mentioned NUREG0800 updates to September, 2007 (i.e. six months prior to submittal of the remainder of the CCNPP Unit 3 COL application), no new applicable NRC Bulletins or Generic Letters were issued. Therefore, the conformance assessment for CCNPP Unit 3 relative to operational experience is satisfied by the conformance assessment provided in Section 1.9.2 above.} 1.9.5 Advanced and Evolutionary Light-Water Reactor Design Issues Assessment of the conformance with regulatory guidance identified with a code of ”N/ACOL” in Table 1.94 of the U.S. EPR FSAR was performed. {CCNPP Unit 3} conforms to the applicable regulatory guidelines in effect six months prior to the submittal date of the COL application that were assigned an assessment code of ”N/ACOL” in Table 1.94 of the U.S. EPR FSAR. 1.9.6 References {AREVA, 2009. U.S. EPR Conformance with Standard Review Plan (NUREG0800) Technical Report, ANP10292, Revision 1, AREVA, May 2009.} CCNPP Unit 3 1-53 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 Conformance with Regulatory Criteria Table 1.9-1— {Conformance with Regulatory Guides} (Page 1 of 3) RG / Rev Description Exception Descriptions Reference Division 1 Regulatory Guides FSAR 13.1.3.1 Licensed personnel are not able to meet Regulatory Guide 1.8, FSAR 13.2 Rev. 3 operating plant experience requirements on CCNPP Unit Technical 3. Regulatory Guide 1.8, Rev. 2, Regulatory Position C.1.b will be Specifications followed instead for a cold licensing program. 5.3.1 1.8, R3 Qualification and Training of Personnel for Nuclear Power plants Quality Control and Quality Assurance personnel will meet education and experience requirements in accordance with the FSAR 13.1.3.1 approved Quality Assurance Program Description. The Quality Assurance Manager will approve the use of an alternative for the formal education and experience requirements for Quality Assurance positions in accordance with the approved Quality Assurance Program Description. FSAR 13.1.3.1 1.16, R4 The annual operating report and monthly operating report are submitted in accordance with Technical Specifications. Event Reporting of Operating Information reporting is performed in accordance with 10 CFR 50.72 and —Appendix A Technical 50.73 utilizing the guidance of NUREG1022. Technical Specifications Specifications reporting requirements are implemented, as required. License Condition and Technical Specifications 1.23, R1 Meteorological Monitoring Programs for Nuclear Power Plants Atmospheric moisture data for the UHS and CWS cooling towers are not taken on site. They are taken from the closest source of atmospheric moisture data at the Patuxent River Naval Air Station. The meteorological tower is at a different elevation than plant grade to assure the tower is on a level, open terrain. No wind shield installed on the precipitation gauge prior to June 2009. A digital data sampling rate of 10 seconds will be used instead of 5 seconds. FSAR 2.3.3.1.7, 2.3.1.2.2.13, and 2.3.3.2.7 ER 6.4.1, 6.4.1.7, and 6.4.2.7 1.28, R3 Quality Assurance Program Requirements Quality Assurance Program Requirements are in accordance with the approved Quality Assurance Program Description. FSAR 17.5 1.30, R0 Quality Assurance Requirements for the Installation, Inspection, and Testing of Instrumentation and Electric Equipment Quality Assurance requirements for the installation, inspection, and testing of instrumentation and electric equipment are in accordance with the approved Quality Assurance Program Description. FSAR 17.5 1.33, R2 Quality Assurance Program Requirements (Operation) Quality Assurance Program Requirements for Operation are in accordance with the approved Quality Assurance Program Description. FSAR 17.5 1.38, R2 Quality Assurance Requirements for Quality Assurance requirements for packaging, shipping, Packaging, Shipping, Receiving, receiving, storage, and handling of items are in accordance Storage, Handling of Items for with the approved Quality Assurance Program Description. WaterCooled Nuclear Power Plants FSAR 17.5 1.39, R2 Housekeeping Requirements for Watercooled Nuclear Power Plants Quality Assurance requirements for housekeeping are in accordance with the approved Quality Assurance Program Description. FSAR 17.5 1.70, R3 Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants (LWR Edition) The format and content of the FSAR follows Regulatory Guide 1.206 and the U.S. EPR FSAR. FSAR 1.1.6 CCNPP Unit 3 1-54 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7 FSAR: Chapter 1.0 Conformance with Regulatory Criteria Table 1.9-1— {Conformance with Regulatory Guides} (Page 2 of 3) RG / Rev Description Exception Descriptions Reference Quality Assurance Program Requirements for installation, inspection and testing of structural concrete and structural steel during the construction phase of nuclear power plants are in accordance with the approved Quality Assurance Program Description. FSAR 17.5 Quality Assurance Program Requirements for installation, inspection, and testing of mechanical equipment and systems are in accordance with the approved Quality Assurance Program Description. FSAR 17.5 Soil boring quantities, locations, and depths, vertical deviation measurements, and soil core photography deviate from Regulatory Guide 1.132. FSAR 2.5.4.2.2.2 Laboratory Investigations of Soils 1.138, R2 and rocks for Engineering Analysis and Design of Nuclear Power Plants More recent ASTM or EPA standards were used that are equivalent to the outofdate and uncommon test procedures discussed in Regulatory Guide 1.138, R2 FSAR 2.5.4.2.4 Procedures and Criteria for 1.198, R0 Assessing Seismic Soil Liquefaction at Nuclear Power Plant Sites Aerial photography was not conducted to plan and conduct the subsurface investigation due to uniformity in geologic conditions between the existing CCNPP Units 1 and 2 and CCNPP Unit 3. FSAR 2.5.4.8.2 EPRI Report TR1014381 was used in lieu of EPRI Report 1013105. The former report is the final EPRI report versus the latter update report cited in the Regulatory Guide. There is no technical difference between the recommended CEUS sigma values and report conclusions. Equation 7 in Appendix D, Step 3, Determining Controlling Earthquakes, was not used because it is incorrect. A corrected equation was used instead. FSAR 2.5.2.4.5 The mean magnitude and mean distance contributing to high frequency ground motion was used versus the average magnitude and average distance specified in Appendix D. Use of the mean provides a more accurate description of the magnitudes and distances. FSAR 2.5.2.4.6 1.94, R1 Quality Assurance Requirements for Installation, Inspection and Testing of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants Quality Assurance Requirements for Installation, Inspection, and Testing 1.116, R0 of Mechanical Equipment and Systems 1.132, R2 Site Investigation for Foundations of Nuclear Power Plants A PerformanceBased Approach to 1.208, R0 Define the SiteSpecific Earthquake Ground Motion Division 4 Regulatory Guides 4.4, R0 Reporting Procedure for Mathematical Models Selected to Predict Heated Effluent Dispersion in Nuclear Water Bodies NUREG1555 Section 5.3.2 was utilized. ER 5.3.2 Division 5 Regulatory Guides None Division 8 Regulatory Guides 8.2, R0 Guide for Administrative Practices in Radiation Monitoring CCNPP Unit 3 The reference to 10 CFR 20.401 is no longer valid in the current version of 10 CFR Part 20 ANSI N13.21969 was reaffirmed in 1988. 1-55 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED FSAR 12.5 Rev. 7 FSAR: Chapter 1.0 Conformance with Regulatory Criteria Table 1.9-1— {Conformance with Regulatory Guides} (Page 3 of 3) RG / Rev Description Exception Descriptions Reference 8.4, R0 The reference to 10 CFR 20.202 (a) and 20.401 is no longer valid in the current version of 10 CFR Part 20. ANSI N13.51972 was reaffirmed in 1989. The two performance criteria specified in Regulatory Guide 8.4 DirectReading and (accuracy and leakage) for these devices are met using IndirectReading Pocket Dosimeters acceptance standards in ANSI N3221997 ”American National Standard Inspection, Test, Construction, and Performance Requirements for Direct Reading Electrostatic/ Electroscope Type Dosimeters.” FSAR 12.5 8.6, R0 Standard Test Procedure for GeigerMuller Counters The instrument calibration program is based upon criteria in ANSI N3231978 (R1993) ”Radiation Protection Instrumentation and Calibration.” FSAR 12.5 8.8, R3 Information Relevant to Ensuring That Occupational Radiation Exposures at Nuclear Power Stations Will Be As Low As Reasonably Achievable Section C.3.b – Regulatory Guide 1.16 Section C.1.b (3) data is no longer reported. Reporting is also no longer required for Section C.1.b (2). Sections C.4.b – C.4.d – Conformance is with the latest revision of NUREG0041. FSAR 12.5 CCNPP Unit 3 1-56 © 2007-2010 UniStar Nuclear Services, LLC. All rights reserved. COPYRIGHT PROTECTED Rev. 7